These reports have been declassified and issued by kind permission of: y British Energy Group Plc., UK y Magnox Electric Ltd., UK y Nexia Solutions Ltd., UK
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Research & Technology
FISPIN10 Validation Review
Authors D R Parker and R W Mills
Date 19 March 2001
Checked by : P Little Date 19 March 2002
Approved by : C M Hassall Date 19 March 2002
This work was completed for the Industry Management Committee (IMC) under British Energy contract number BWD/40035986, entitled FISPIN Code Validation Review. (IMC reference number RPS/GNSR/5030).
Confidentiality and Intellectual Property Rights "The information contained in this report has been produced for British Energy Generation Ltd on behalf of the Industry Management Committee (IMC) thus is the joint property of British Energy Generation Ltd and British Nuclear Fuels plc and their successor companies. The information is to be held strictly in confidence by the originators and recipients, unless the contract specifies otherwise. No disclosure is to be made to a third party without written agreement from J Martin, British Energy Generation Ltd, Barnett Way, Barnwood, Gloucester, GL4 7RS. Further any Intellectual Property Rights arising from or contained in the report are the joint property of British Energy Generation Ltd and British Nuclear Fuels plc, and their successor companies, as such are subject to the same obligation of confidence on the originator and recipients as set out above and may only be used in accordance with the contract."
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EXECUTIVE SUMMARY The most recent comprehensive validation study for the fuel inventory code FISPIN was published in 1994. Since this work was completed, there have been significant developments to the nuclear data libraries recommended for use with the code and the irradiation of spent fuel has increased significantly beyond that covered in the 1994 report. This report is an extended validation study to underpin the continued use of FISPIN in predicting spent fuel inventories and decay heat for Magnox, AGR and PWR fuel. The study is in two parts; firstly, validation of the recommended calculational route by comparison with experimental results and secondly, verification using similar codes and alternative nuclear data libraries. In the case of the validation study, no new Magnox data was available and the work was carried out on the data used for the 1994 report. A larger amount of experimental AGR data has been used, although it is contemporaneous with that used in the 1994 report. The results of the validation for Magnox fuel appear a little worse than in the previous study and those for AGR fuel are similar. The PWR validation study used experimental data from three different reactors; Obrigheim, Calvert Cliffs and Goesgen. The data from Obrigheim was used in the previous study and there is little difference between the results of that study and the present one. In general, the results from the different fuel types show similar characteristics. In particular, U235 is over-predicted by on average approximately 5%. The over-prediction increases as the irradiation increases - a small error in the burnout rate of U235 is emphasised increasingly as the fraction of U235 lost increases. Pu239 is over-predicted by approximately 10%. This tends to increase with irradiation, although the over-prediction for Magnox fuel is particularly high. The over-prediction of Pu239 contributes to the 5% over-prediction of plutonium. Since U235 and Pu239 contribute the majority of fissions, it is important that they are modelled accurately. Cm244 is usually under-predicted for all fuel types. For AGR and PWR fuel this is by an average of almost 20%, and there is no discernible variation with irradiation. For Magnox fuel the under- prediction is almost 50% on average, but the magnitude of the under-prediction decreases as irradiation increases. Eu154 was measured in a number of experiments and the results show that it is over-predicted, sometimes by as much as 100%. The predictions of decay heat have been compared to the measurements upon PWR assemblies. Results show a small over-prediction of up to 6%. The predictions of neutron emission rate have been compared to the measurements upon AGR samples. Results show an under-prediction of approximately 20%, which can be attributed to the under-prediction of Cm242 and Cm244. Comparisons with other codes systems provide some indication of the validity of the nuclides for which no measurement data exist. This has been done in this report - the results of the WIMS8A- TRAIL1A-FISPIN10 route have been compared to those from two other routes: a) the reactor physics code CASMO4, cross-section processing code CAS2FIS, and FISPIN10 (using data libraries derived from JEF2.2) and
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 3 of 115 RAT 1972 Issue 02 RAWG/P(01)04 b) the SCALE4.4a processing package which includes the inventory code ORIGEN-S (using data libraries derived predominantly from the ENDF-B/V and ENDF-B/VI data libraries). Overall the agreement between the predictions of CASMO/FISPIN with those of WIMS/FISPIN is good, but there are some large differences at certain combinations of fuel parameters. In particular, U234 shows a deviation of approximately –50% in the all the high irradiation cases and several of the higher actinides show a deviation of approximately +50% in the low irradiation cases for AGR fuel. When using the SCALE route the predictions of many quantities are similar to those of the WIMS/FISPIN route, but there are several for which differences are large (over 50%). The differences in the gamma spectrum at the longest cooling times are very large indeed, with SCALE predicting over a thousand times more emission in some energy groups. It has been shown that some of the differences can be explained by differences in the gamma emission data used. It is important to note that that SCALE has not been validated for use in modelling the burnup of either Magnox or AGR fuel and there are no recommended routes for such calculations. The WIMS input files, the FISPIN input and output files, and all the results of the verification are available on CD-ROM obtainable from the authors.
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HISTORY
Issue Number Date Comments Draft 01 1 May 2001 Draft for customer comment Issue 01 8 August 2001 Issue 02 19 March 2002 Magnox validation redone using densities averaged over three dimensions and the values of several Goesgen measurements corrected
DISTRIBUTION
Name Location IMC Mr D Anderson British Energy Generation (UK) Ltd, Peel Park Mr S Campbell British Energy Generation Ltd, Barnwood Mr D MacNaughton British Energy Generation (UK) Ltd, Peel Park Mr G Airey British Energy Generation Ltd, Barnwood Dr PK Dickens BNFL Sellafield Mr AJ Cooper BNFL Risley Dr MP Knight British Energy Generation Ltd, Barnwood Mr G Adderley (3 copies) NII Bootle Dr DN Simister NII Bootle Dr DJ Edens BNFL Berkeley Dr DA Thornton BNFL Berkeley RAWG P K Hutt British Energy Generation Ltd, Barnwood J S Martin British Energy Generation Ltd, Barnwood E Johnston British Energy Generation Ltd, Barnwood G S Whiley British Energy Generation Ltd, Barnwood M T Friend British Energy Generation Ltd, Barnwood J H Kirby British Energy Generation Ltd, Dungeness B Power Station S Rushworth British Energy Generation Ltd, Hartlepool Power Station V Roberts British Energy Generation Ltd, Heysham 1 Power Station B J Callender British Energy Generation Ltd, Heysham 2 Power Station A Skirrow British Energy Generation Ltd, Hinkley Point B Power Station M Scott British Energy Generation Ltd, Hunterston B Power Station JW Johnston British Energy Generation Ltd, Torness Power Station D Gray British Energy Generation (UK) Ltd, Peel Park J L Hutton AEA Technology plc, Winfrith Technology Centre, Dorchester. R E Sunderland NNC Ltd, Booths Hall Summary Only R S Overton British Energy Generation Ltd, Barnwood
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S Fairbairn British Energy Generation Ltd, Barnwood J Gotts British Energy Generation Ltd, Barnwood F M Evans British Energy Generation Ltd, Barnwood M Javadi British Energy Generation Ltd, Sizewell B Power Station A Douglas British Energy Generation (UK) Ltd, Peel Park D Bishop British Energy Generation (UK) Ltd, Peel Park R J Firth BNFL Berkeley
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Contents 1. Introduction ...... 10 1.1 Computer Codes and Data Libraries ...... 10 1.2 Data Source ...... 11 1.3 Modelling Methods ...... 11 1.4 Number Formats and Experimental Errors...... 11 2. Magnox...... 12 2.1 Experimental Measurements ...... 12 2.2 Modelling ...... 12 2.3 Results ...... 13 3. AGR...... 13 3.1 Modelling ...... 13 3.2 Results ...... 14 4. PWR Validation ...... 15 4.1 Obrigheim...... 15 4.1.1 Experimental Measurements ...... 15 4.1.2 Modelling ...... 15 4.1.3 Results ...... 16 4.2 Calvert Cliffs ...... 16 4.2.1 Experimental Measurements ...... 16 4.2.2 Modelling ...... 17 4.2.3 Results ...... 17 4.3 Goesgen ...... 17 4.3.1 Experimental Measurements ...... 18 4.3.2 Modelling ...... 18 4.3.3 Results ...... 18 5. Data Summed Over Nuclides ...... 19 5.1 Decay Heat ...... 19 5.1.1 Differential Fission Product Decay Heat Measurements...... 19 5.1.2 Integral Decay Heat Measurements...... 20 5.2 Neutron Emission ...... 21 5.2.1 Neutron Emission Measurements...... 21 6. Verification...... 21 6.1 CASMO Comparison ...... 22 6.2 SCALE Comparison...... 23 7. Conclusion...... 25 8. References ...... 27 Appendix A : FISPIN and WIMS Parameters...... 30 Appendix B : Tables...... 32 Appendix C : Figures...... 87 Appendix D : WIMS Input Examples ...... 94
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Tables Table 1: Nuclides of interest...... 32 Table 2: Fuel types and the ranges of parameters considered in this paper...... 33 Table 3: Irradiation parameters for the Magnox samples...... 33 Table 4: Cooling times for the Magnox samples...... 33 Table 5: Magnox results...... 34 Table 6: Characteristics and reactor parameters of the AGR samples...... 35 Table 7: Cooling times (days) for the AGR sample measurements...... 38 Table 8: AGR results for the uranium isotopes...... 39 Table 9: AGR results for the plutonium isotopes (with respect to plutonium)...... 41 Table 10: AGR results for the plutonium isotopes (with respect to uranium)...... 43 Table 11: AGR results for the neodymium isotopes (with respect to neodymium)...... 45 Table 12: AGR results for the neodymium isotopes (with respect to uranium)...... 47 Table 13: AGR results for Nd148, plutonium and minor actinides...... 49 Table 14: AGR results for fission product activity...... 51 Table 15: Irradiation history of the Obrigheim assemblies...... 52 Table 16: Obrigheim sample characteristics and irradiations...... 52 Table 17: Obrigheim results for uranium isotopes...... 53 Table 18: Obrigheim results for plutonium isotopes...... 54 Table 19: Obrigheim results for minor actinides...... 55 Table 20: Obrigheim results for Nd148, Cs134, Cs137 and Eu154...... 56 Table 21: Obrigheim results for krypton isotopes with respect to Kr86 and xenon isotopes with respect to Xe134...... 57 Table 22: Irradiation history of the Calvert Cliffs Unit 1 reactor...... 58 Table 23: The rods from Calvert Cliffs analysed as part of the ATM programme...... 58 Table 24: Simplified irradiation histories representative of those of the ATM samples...... 58 Table 25: Identification, height, irradiation, and mean on power rating for the ATM samples....59 Table 26: Calvert Cliffs results for the uranium isotopes...... 60 Table 27: Calvert Cliffs results for the plutonium isotopes...... 60 Table 28: Calvert Cliffs results for plutonium...... 61 Table 29: Calvert Cliffs results for the minor actinides...... 61 Table 30: Calvert Cliffs results for Se79, Sr90 and Tc99...... 61 Table 31: Calvert Cliffs results for Sn126, Cs135 and Cs137...... 61 Table 32: Calvert Cliffs results for C14 and I129...... 62 Table 33: Irradiation history of the Goesgen reactor...... 63 Table 34: Goesgen samples analysed as part of the Ariane programme...... 63 Table 35. Reported irradiation histories of the Goesgen samples (used in the WIMS models)....63 Table 36. Average boron concentrations...... 63 Table 37: Goesgen results for the heavy nuclides...... 64 Table 38: Goesgen results for the fission products...... 65 Table 39: Assembly information, irradiation, cooling and measured decay heat...... 66 Table 40: FISPIN predictions of heat and their comparison with measured values...... 67 Table 41: Contributions to the decay heat of fission products, heavy elements, fuel impurities and structural materials...... 68 Table 42: Characteristics of the AGR samples...... 69 Table 43: Comparison of calculated and experimental neutron emission rates from each sample...... 69
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Table 44: Comparison of calculated and experimental values of Cm242 and Cm244 present in each sample...... 69 Table 45: Reactors and fuel parameters used for verification...... 70 Table 46: Decay periods used in verification...... 70 Table 47: The ratio of CASMO to WIMS predictions at shutdown...... 71 Table 48: The ratio of CASMO to WIMS predictions at the maximum cooling times...... 73 Table 49: Summary of the ratio CASMO to WIMS predictions over all cooling times...... 75 Table 50: Gamma groups used in FISPIN and SCALE...... 75 Table 51: The ratio of CASMO to WIMS predictions of the gamma spectrum (γ/s) at shutdown...... 76 Table 52: The ratio of CASMO to WIMS predictions of the gamma spectrum (γ/s) at the maximum cooling times...... 77 Table 53: The ratio of SCALE to WIMS predictions at shutdown...... 78 Table 54: The ratio of SCALE to WIMS predictions at the maximum cooling times...... 80 Table 55: Summary of the ratio SCALE to WIMS predictions over all cooling times...... 82 Table 56: The ratio of SCALE to WIMS predictions of the gamma spectrum (γ/s) at shutdown.83 Table 57: The ratio of SCALE to WIMS predictions of the gamma spectrum (γ/s) at the maximum cooling times...... 84 Table 58: Overall results for the heavy nuclides...... 85 Table 59: Overall results for the activation and fission products...... 86 Table 60: Overall results for decay heat and neutron emission...... 86
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Figures Figure 1: Calculation over experiment for U235 as a function of irradiation...... 87 Figure 2: Calculation over experiment for U235 as a function of U235 depletion...... 87 Figure 3: Calculation over experiment for Pu239 as a function of irradiation...... 88 Figure 4: Calculation over experiment for plutonium as a function of irradiation...... 88 Figure 5: Calculation over experiment for Cm244 as a function of irradiation...... 89 Figure 6: Calculation over experiment for Eu154 as a function of irradiation...... 89 Figure 7: The decay heat from fission products following a U235 fission pulse compared to the results of Tobias...... 90 Figure 8: The decay heat from fission products following a Pu239 fission pulse compared to the results of Tobias...... 90 Figure 9: The decay heat from fission products following a Pu239 fission pulse compared to the results of Dickens...... 91 Figure 10: The decay heat from fission products following a Pu241 fission pulse compared to the results of Dickens...... 91 Figure 11: The decay heat from fission products following a U238 fission pulse compared to the results of Akiyama...... 92 Figure 12: The fission product decay heat following a U235 fission pulse calculated using JEF-2.2 compared to the results of Tobias...... 93 Figure 13: The fission product decay heat following a Pu239 fission pulse calculated using JEF-2.2 compared to the results of Tobias...... 93
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1. Introduction The last general validation study of the fuel inventory code FISPIN [1] was published by Burstall in 1994 [2]. This work summarised the validation for Magnox, AGR and PWR calculations based upon the use of FISPIN 6 together with a mixture of libraries based upon UKNDL and JEF1. An update of this work is required for two reasons; firstly, the move to JEF2.2 nuclear data [6] and secondly, the increase in fuel irradiations. In particular, a task carried out with IMC funding in 1997 produced a draft document detailing how FISPIN should be used to carry out inventory and decay heat calculations for AGR fuel. This document is intended as a component of British Energy’s AGR physics handbook. The document recommended the use of FISPIN7 with decay data taken from JEF2.2 and cross-section data calculated by WIMS and TRAIL [4,5], the WIMS library being derived from JEF2.2. This recommendation will be revised to replace the use of FISPIN7 by FISPIN10, the most recent FISPIN release [3]. A revised validation summary is therefore required to support the above recommendation and also to provide a basis for comparable recommendations for modelling PWR and Magnox fuel. To achieve this, an IMC funded contract was created between British Energy and BNFL, under which BNFL would perform the study with guidance from British Energy. The validation review has been performed in two parts: The first consists of “full” validation by comparing predictions against experimental data and the second, the verification of predictions by comparing the results of three calculational routes where alternative codes and nuclear data combinations have been used. The nuclides of interest are listed in Table 1.
1.1 Computer Codes and Data Libraries The comparison against experimental data was performed using the reactor physics code WIMS8A [4] (with library W97DG69V1), cross-section processing code TRAIL1A [5] (with library DB10TRAIL69), and FISPIN10 [3] (with JEF2.2 decay files). The reactor physics code WIMS is used to model the burnup of a fuel assembly and calculate the fine group burnup-dependent neutron flux and a small number of fine group burnup-dependent cross-sections for which self-shielding effects are important. The code TRAIL then calculates three group burnup-dependent cross-sections using the WIMS fine group flux and its own library of fine group cross-sections. The fuel inventory code FISPIN is then used to calculate the spent fuel inventory using these cross-sections and decay data and fission yields from JEF2.2. The verification was performed by comparing the results of the WIMS-TRAIL-FISPIN route with those from two other routes: a) the reactor physics code CASMO4 [7] (with JEF2.2 library), cross-section processing code CAS2FIS [8] (with library DB10TRAIL69), and FISPIN10 [3] (with JEF2.2 decay files) and b) the SCALE4.4a processing package which includes the inventory code ORIGEN-S [9] (and using data libraries derived from ENDF-B/V and ENDF-B/VI).
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The data contained in the JEF2.2 decay file for the gamma emission from Pr144 is incorrect. For the work in this paper, all of the data pertaining to Pr144 and Pr144M has been replaced by that contained in UKPADD-6 [10].
1.2 Data Source The experimental data used in validation consists of the results of destructive and non- destructive analysis of irradiated fuel. This paper considers analysis of fuel from Magnox reactors (Hunterston A and Bradwell), AGRs (Hinkley Point B and Hunterston B) and PWRs (Obrigheim, Calvert Cliffs 1 and Goesgen). Also considered are the measurements of the decay heat following a fission pulse (U235, U238, Pu239), the heat output of PWR assemblies (San Onofre, Point Beach (WEPCO), Turkey Point) and the neutron emission arising from several AGR samples (Hinkley Point B). A summary of the characteristics of the samples analysed is shown in Table 2.
1.3 Modelling Methods In order to predict the characteristics of the irradiated fuel samples, information is required regarding their initial composition, their geometrical characteristics and those of the reactor in which they were irradiated, specific conditions of the sample and reactor during irradiation (such as fuel temperature, moderator temperature, coolant pressure, etc.), and the time from the end of irradiation to analysis (the “cooling” time). Many of these parameters are reported by the experimentalists together with their results, and others are obtainable from publications such as the World Nuclear Industry Handbook. However, there usually remain a number of parameters whose values are unknown and for which assumptions must be made. In addition, in both WIMS and FISPIN, the use of some keywords and the values of various computational parameters are at the discretion of the user. Some of the assumptions used for this work are discussed in Appendix A. In particular, the derivation of the initial U234 and U236 content of the fuel is included and this has been used unless otherwise stated.
1.4 Number Formats and Experimental Errors The format used in this paper for the experimental results is identical to that used in the source documents. The results of FISPIN are given in the same format as the experimental results but always to four significant figures. The calculated (FISPIN) over experimental value (C/E) and its error is always given to two decimal places (except when comparing gamma spectra). This sometimes leads to an error of zero, which should be interpreted as meaning less than 0.005. The mean value of the C/E results for a nuclide are reported, together with their standard deviation (SD), calculated using
1 æ 1 n ö 2 SD = ç ()x − x 2 − i è n 1 i=1
where n is the number of results and x is their mean. The mean and standard deviation are normally given to two decimal places. If this resulted in a zero value for the standard deviation, the number of decimal places has been increased for both the mean and standard deviation until a non-zero value was obtained.
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The errors reported by the experimentalists are to one sigma and refer to the uncertainty of the analytical process. The errors on the Obrigheim results also contain uncertainties from cutting losses and in the cutting position.
2. Magnox Analysis of several samples of irradiated Magnox fuel was performed during the years 1975 and 1976 [13, 14]. Five samples were obtained from fuel elements irradiated in the Hunterston A power station (labelled A, B, C, A’ and B’) and one from the Bradwell power station (labelled D). The fuel elements were furthest removed from control rods and absorbers and near the middle of the channel axially. The samples, which were complete cross-sections of fuel and cladding, were cut from the centre of each fuel element. Samples A and A’ and B and B’ came from adjacent positions, respectively. Sample irradiations ranged from 3 to 9 GWd/t. The isotopic measurements for samples A, B, C and D were performed at the then UKAEA’s laboratory at Harwell.
2.1 Experimental Measurements The experimental measurements contained in reference 14 were used. The results are also contained in reference 13, although the values of Zr95/U do not agree for samples C and D. In deciding which values to use, the same choices were made as in reference 2, although there is no evidence that these are correct. The Cs134/U (Bq/g) ratio has been derived from the Cs134/Cs137 activity ratio and the Cs137/U (Bq/g) ratio. The mass ratio of the plutonium isotopes to uranium has also been derived from their atom ratio to plutonium and the plutonium to uranium mass ratio.
2.2 Modelling A WIMS8 model of the Hunterston A reactor was created at a rating of 2.7 MW/t and continuous irradiation. Burnup-dependent cross-section libraries were then produced using TRAIL. Using these cross-section libraries, FISPIN was used to derive a relationship between irradiation and the Nd148/U mass ratio. The relationship could then be used to determine the irradiations of the samples A, B and C from the measured Nd148/U ratio. The same process was applied to derive the irradiation of the Bradwell sample (D) using a rating of 2.4 MW/t. The power histories were obtained from Figure 1 of reference 13. The first power on and power off periods were adjusted to give the same total on-power time and dwell time shown in Table 10 of reference 2. However, for sample D the ratings and on-power time given in Table 10 of reference 2 are inconsistent. Therefore the first power on and power off periods were adjusted equally to give the same dwell time only. The samples were assumed to have been irradiated at a constant rating and these were derived to achieve the appropriate final irradiation. However, in the case of Sample D, the rating was reduced by 7% after an irradiation of 6552 MWd/t owing to the derating of the Bradwell reactor. These parameters are summarised in Table 3. The cooling parameters of the samples are given in Table 4. A WIMS model was performed for each of the four samples using the derived ratings. (The mean rating was used for sample D). In these models, the density of the core
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graphite was taken from the ARGOSY 4MC input decks contained in reference 15. Whilst the WIMS model is a two-dimensional representation, all densities were scaled to the length of the uranium rod (as suggested in reference 16), in order to give the correct masses over three dimensions. The fuel and moderator temperatures were taken from reference 13, although it is not stated from where these were obtained. No attempts were made to model the perturbing effects of nearby non-fuel channels. Burnup-dependent cross-section libraries were created using TRAIL. Using the libraries produced by TRAIL, FISPIN runs were performed using the appropriate irradiation history. An example of the input to WIMS for this reactor system is given in Appendix D and some of the assumptions and modelling methods relating to WIMS and FISPIN are discussed in Appendix A.
2.3 Results The results are presented in Table 5. The calculated/experimental (C/E) values for the uranium isotopes are within 10% except for U234, which is within 20%. The C/E for U235 for sample D is high, although within the uncertainty. The C/E values are approximately 10% low for Pu240 and Pu241 (with respect to uranium), are approximately 30% low for Pu238 and Pu242, and are 15% high for Pu239. Overall, plutonium is over-predicted by 6%. Both Cm242 and Cm244 are under-predicted by almost 50%. The C/E values for the plutonium and curium isotopes increase with increasing irradiation. The C/E values for the fission products are generally within 20%, although those of Nb95 are much larger at nearer 100%. Overall, the results appear a little worse than those of reference 2.
3. AGR Considerable post-irradiation examination of AGR fuel was carried out by the then UKAEA at their Harwell and Winfrith laboratories in the late seventies and throughout the eighties. The results have been collated in reference 17. The fuel was irradiated in Hinkley Point and Hunterston reactors. The initial U235 enrichments ranged from 1.542% to 2.55% and irradiations ranged from 1 to 26 GWd/t. The samples were often composed of pellets from the same axial location within three or four pins of the same ring (inner, middle and outer). The samples were referenced through a PIE reference number, to which has been added a single digit to give a unique identification number. The characteristics and reactor parameters of the samples are given in Table 6, and the cooling periods in Table 7.
3.1 Modelling A WIMS8 model of the Hinkley Point B reactor was created at a rating of 10 MW/t and continuous irradiation. Using the cross-section libraries produced, FISPIN was used to derive a relationship between irradiation and the Nd148/U mass ratio. This relationship could then be used to determine the irradiations of the samples from the measured Nd148/U ratio.
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For each of the six different enrichment, pellet bore and stage (sleeve design) combinations a WIMS8 run was performed for the inner, middle and outer ring of pins. The dimensions and densities of the graphite sleeves and bulk moderator were obtained from reference 18, in which the densities were scaled to give the correct masses over three dimensions. An average rating for those samples within each set together with a continuous irradiation were used in this model. Burnup-dependent cross-section libraries were then created using TRAIL. The irradiation histories for the individual reactors were obtained from the station records. These were simplified into several periods of constant power. It was assumed that a sample attained the same fraction of its final irradiation in each on-power period as the reactor it was in, the rating within each period adjusted accordingly (Appendix A). FISPIN runs could then be performed, using the cross-section libraries created as described above. The predicted Nd148/fuel mass ratio was compared to the experimental result and the ratio of the values used to adjust the final irradiation of the samples. The resulting irradiation is shown in Table 6. The FISPIN runs were then repeated with the ratings adjusted accordingly. An example of the input to WIMS for this reactor system is given in Appendix D and some of the assumptions and modelling methods relating to WIMS and FISPIN are discussed in Appendix A.
3.2 Results The results are presented in Table 8 (uranium isotopes), Table 9 (plutonium isotopes with respect to plutonium), Table 11 (neodymium isotopes with respect to neodymium), Table 13 (Nd148, plutonium and minor actinides with respect to uranium) and Table 14 (fission product activity). In Table 10 the masses of the plutonium isotopes with respect to uranium are shown. These were calculated from the isotopic ratios with respect to plutonium and the Pu/U ratio. In Table 12 the masses of the neodymium isotopes with respect to uranium are shown. These were calculated from the isotopic ratios with respect to neodymium and the Nd148/U ratio. The majority of C/E values for the uranium isotopes are within 20%, except for U234 for which a number of results from Harwell appear abnormally low. The C/E for U235 is high and increases with irradiation as shown in Figure 1. The C/E values are within 20% for the majority of the plutonium isotope results (with respect to uranium). Overall, plutonium is over-predicted by a few percent but with fluctuations within -5 to +10%. Many of the deviations in the C/E value for plutonium and its isotopes for the lowest irradiation sample, B4001, are large. Am241 is predicted within 20% and overall Cm242 and Cm244 are under-predicted by approximately 5% and 10% respectively. The C/E values for the fission products cover a wide range, some being very large. For example, Sb125 is over-predicted by 100%, whereas Eu155 is under-predicted by 40%. Overall, the results appear similar to those of reference 2.
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4. PWR Validation
4.1 Obrigheim Analysis of fuel from the Obrigheim PWR was carried out during 1977 and 1978 [19, 20, 21]. PIE of six fuel pins taken from the reactor was performed at two European laboratories, Ispra and Karlsruhe. Four fuel pins were taken from fuel assembly BE124 and two from BE210, with assembly averaged irradiations of 29 GWd/t and 30 GWd/t, respectively. The assemblies were composed of 180 fuel pins of uranium dioxide with initial 235U enrichments of 3% and 2.83%, for BE124 and BE210 respectively. Samples were taken from several axial locations giving a total of 23. Some of the samples were analysed at both Ispra and Karlsruhe, enabling a comparison between their results. The irradiation histories and declared assembly irradiations are shown in Table 15. Sample characteristics and reactor parameters of the samples are given in Table 16.
4.1.1 Experimental Measurements The experimental results were taken from reference 21, excepting the Xe130/Xe134 ratio which was absent from this report but was given in reference 19. In reference 21, the Am241 results were divided into two sets (A and B), and it was suggested that greater reliance should be placed upon set A than B. In addition, the presence of a systematic error was suggested in the Cm242 results of Karlsruhe. The Obrigheim reports refer to the measurement of Am242 when in fact it was of Am242M that was measured. Most of the experimental results have been derived with respect to initial uranium mass and have been corrected back to the end of irradiation. These calculations require the use of nuclear data which was probably different from that contained within JEF-2.2. The depletion of U235 and U238 is given rather than the quantity remaining. The errors reported are to one sigma and refer to the uncertainty of the analytical process and uncertainties arising from cutting losses and in the cutting position. The errors are given only for the measurements performed at Ispra.
4.1.2 Modelling A WIMS8 model of an Obrigheim assembly was created for fuel with an enrichment of 2.92% (the mean of the BE124 and BE210 enrichments), at a rating of 29 MW/t (the average of all the samples) and continuous irradiation. An average boron concentration of 500 µg/g was assumed. Using the cross-section libraries produced, FISPIN was used to derive a relationship between irradiation and the Nd148/U atom ratio. This relationship could then be used to determine the irradiations from the measured Nd148/U ratio. WIMS8 runs were performed for each pin at a rating of 29 MW/t and continuous irradiation. Burnup-dependent cross-section libraries were then created using TRAIL. It was assumed that a sample attained the same fraction of its final irradiation in each on- power period as the assembly it was in, the rating within each period adjusted accordingly (Appendix A). FISPIN runs could then be performed, using the cross-section libraries created as described above. The mean on power rating was then determined using the on power days. The predicted Nd148/fuel atom ratio was compared to the experimental result and the ratio of the values used to adjust the final irradiation of the samples. The
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resulting irradiations and ratings are shown in Table 16. The FISPIN runs were then repeated with the ratings adjusted accordingly. An example of the input to WIMS for this reactor system is given in Appendix D and some of the assumptions and modelling methods relating to WIMS and FISPIN are discussed in Appendix A.
4.1.3 Results The results are presented in Table 17 (uranium isotopes), Table 18 (plutonium isotopes), Table 19 (minor actinides), Table 20 (Nd148, Cs134, Cs137 and Eu154) and Table 21 (krypton and xenon isotopes). The C/E values for the depletion of U235 are good for BE124 but are a few percent low for BE210. The predictions for the other uranium isotopes and the plutonium isotopes are normally within 20%. Pu239 is over-predicted by on average 10%. The results for the minor actinides show large fluctuations but are generally within 30%. Cm244 is usually under-predicted, with an average deviation of minus 10% (ignoring E3 P2 result from Karlsruhe). Cs134 is over-predicted by about 10% and Eu154 is over-predicted by on average 50%. Comparing the calculated/experimental values with those of previous work [22, 23], which used older versions of nuclear data libraries and codes, little difference is seen.
4.2 Calvert Cliffs Analysis of fuel from the Calvert Cliffs Unit 1 PWR was carried out during 1987 [24, 25, 26]. The Materials Characteristics Center at Pacific Northwest Laboratory, USA, selected three assemblies for the Approved Testing Material (ATM) programme that was designed to provide a source of well-characterised spent fuels. The analyses of these assemblies are referred to as ATM-103, ATM-104 and ATM-106. Enrichments were 2.72%, 3.038% and 2.453% respectively and sample irradiations ranged from 13 GWd/t and 47 GWd/t. For one rod from each assembly, radiochemical measurements were made on samples from several axial locations. At many of the locations only C14 and/or I129 were measured, but at three locations in each rod fifteen actinides and six fission products were measured. The duration of each power cycle and shutdown of the Calvert Cliffs Unit 1 reactor is shown in Table 22 and the assembly and rod identifiers are shown in Table 23. Table 24 shows the simplified irradiation history for a rod from each assembly and Table 25 shows the identifiers of the samples, their reported irradiations and the mean on power rating (derived from the irradiation and on power days). The irradiations were derived in the ATM reports from the measured Nd148/U ratio (the value of this ratio is not reported) for three samples in each rod (those locations where the more complete analyses were performed). The irradiations of the other locations were derived using the activity of Cs137 measured during gamma scanning of the rods.
4.2.1 Experimental Measurements The experimental results were taken from the ATM reports [24, 25, 26]. The Cm243 plus Cm244 activity was determined by alpha spectrometry, which cannot distinguish between the two isotopes. However, FISPIN results show that for the samples analysed the Cm244 activity is greater than 98% of the sum.
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4.2.2 Modelling A WIMS8 model of each assembly was performed at a rating of 22 MW/t (the approximate mean on power rating for all three rods) and continuous irradiation. Burnup- dependent cross-section libraries were then created using TRAIL. Using the cross-section libraries produced, a FISPIN run was then performed for each sample using irradiation histories derived from Table 24. It was assumed that a sample attained the same fraction of its final irradiation in each on-power period as the rod it was in, the rating within each period adjusted accordingly (Appendix A). The assembly and reactor data were obtained from the ATM reports [24, 25, 26] and supplemented by values from reference 27, including the average boron concentration (Table 22) and time from shutdown to analysis. The FISPIN runs included fuel impurities. The initial quantities specified were the same as those used in the ATM reports for calculations using the ORIGEN2 code. In particular, the amount of nitrogen present was 24 ppm, 23 ppm and 44 ppm for ATM-103, ATM-104 and ATM-106, respectively, which determines the amount of C14 generated. (A small amount of C14 is also produced from oxygen.) An example of the input to WIMS for this reactor system is given in Appendix D and some of the assumptions and modelling methods relating to WIMS and FISPIN are discussed in Appendix A.
4.2.3 Results The experimental results and FISPIN predictions are scaled to the fuel mass, which changes negligibly during irradiation. The results are presented in Table 26 (uranium isotopes), Table 27 (plutonium isotopes), Table 29 (minor actinides), Table 30 (Se79, Sr90 and Tc99), Table 31 (Sn126, Cs135 and Cs137), and Table 32 (C14 and I129). In Table 28 the plutonium over fuel mass ratio is shown which was calculated by summing the isotopic results. The C/E values are within 10% for all the uranium isotopes bar U234, which is within 20%. The C/E for U235 is high and appears to be increasing with irradiation. The C/E values are within 10% for the majority of the plutonium isotopes. Pu239 is over predicted by an average of 9%. Np237 and Am241 are predicted within about 10%, but overall the sum of Cm243 and Cm244 is under-predicted by approximately 16%. The C/E values for the fission products cover a wide range, some being very large. For example, Se79 and Sn126 are over-predicted by a factor of 5. These are similar to the results of the experimentalists’ own comparison with ORIGEN2 predictions, however there is no suggestion of difficulties in their measurement. The results for C14 are reasonably good, despite uncertainties in the initial nitrogen content.
4.3 Goesgen As part of the “Actinide Research In A Nuclear Element” (ARIANE) programme, three UOX fuel samples were irradiated in the Goesgen PWR and then destructively analysed at the Institute for Transuranium Elements Karlsruhe (ITU) and SCK.CEN during the late 1990s [28]. The results from the two laboratories could be compared to ensure the reliability of the measurements. The samples are referred to as GU1 (analysed at SCK.CEN), GU3 and GU4 (ITU). The liquor solution derived from sample GU3 was divided and analysed at both laboratories, giving GU3’ (SCK.CEN) and GU3 (ITU).
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Enrichments were 3.5% and 4.1% and sample irradiations ranged from 29 GWd/t and 60 GWd/t. The sample GU1 was irradiated in assembly 12-40 during four cycles (12 to 15). Preceding cycles 14 and 15, a number pins surrounding the sample were replaced with fresh fuel. The two samples GU3 and GU4 were irradiated during two cycles in fuel assembly 1601 (16 and 17) before being relocated in assembly 1701 for a further cycle (18). Three pins near the sample pin were also relocated to assembly 1701. The duration of each power cycle and shutdown of the Goesgen reactor is shown in Table 33. Table 34 shows the sample characteristics including the reported irradiations and the mean on power rating (derived from the irradiation and on power days). Table 35 shows the irradiation history for each sample.
4.3.1 Experimental Measurements The experimental results were taken from reference 28.
4.3.2 Modelling The initial U234 content of the uranium was reported in reference 29 and is shown in Table 34. Note the fuel did not contain any U236. The boron content of the water was averaged over the appropriate cycles and is shown in Table 36. Because of the movement of pins between assemblies, the WIMS8 models followed the irradiation history given in Table 35. The models of samples GU3 (GU3’ and GU3) and GU4 were performed in two parts and the resulting TRAIL files combined appropriately. Using the cross-section libraries produced, a FISPIN run was then performed for each sample using irradiation histories in Table 35. The predicted Nd148/fuel mass ratio was compared to the experimental result and the ratio of the values used to adjust the final irradiation of the samples. The resulting irradiation is shown in Table 34. The FISPIN runs were then repeated with the ratings adjusted accordingly. An example of the input to WIMS for this reactor system is given in Appendix D and some of the assumptions and modelling methods relating to WIMS and FISPIN are discussed in Appendix A.
4.3.3 Results The experimental results and FISPIN predictions were scaled to the fuel mass, which changes negligibly during irradiation. The ratios of the FISPIN predictions to the experimental results are presented in Table 37 (heavy elements) and Table 38 (fission products). Table 37 includes the results for plutonium, which were calculated by summing the isotopic results. The experimental values cannot yet be reported outside of the programme’s participants. The C/E values are large for U234 and U235 (up to 46% high). Pu239 and Pu241 are over-predicted, whereas Pu242 and Pu244 are under- predicted (the latter by almost 50%). Am241 is over-predicted, by greater than 20% in most cases, and Cm244 is under-predicted by about 20%. The C/E values for most of the fission products are reasonable, but there are a few that show large discrepancies. In particular, Sb125 (3 times too great) and Eu154 (over +50%). It should be noted that the results of the ARIANE programme are still being analysed and discussed by the participants.
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5. Data Summed Over Nuclides
5.1 Decay Heat When irradiated spent fuel has been removed from a reactor, it will continue to generate heat from the radioactive decay of the nuclides present. The magnitude of the decay heat will depend on the reactor system, fuel type, initial nuclide composition, the detailed irradiation history, and the cooling time. For the first 50-80 years, fission products dominate the decay heat, after which heavy elements become dominant. At short cooling times the decay heat from the heavy element group is dominated by the decay of U239 and Np239, with half-lives of 23.47 ± 0.05 minutes and 2.355 ± 0.004 days respectively (data from JEF-2.2 radioactive decay file). After these have decayed (~5 days) the Cm242 becomes the most significant contributor for about two years, after which Pu238 and Cm244 take over, followed later by Am241 and Pu240. At short cooling times the decay heat is dominated by many short-lived fission products whose decay characteristics and fission yields are not well known. In contrast, at longer cooling times (greater than half a year) relatively few fission products make significant contributions to decay heat (about 10 contributing 90% of fission product heating). The main contributors to fission product decay heat at cooling times greater than half a year are Sr90, Y90, Zr95, Nb95, Tc99, Rh106, Sb126, Sb126M, I132, Cs134, Cs137, Ba137M, La140, and Pr144. (The nuclides that contribute the greatest fraction change as cooling time increases.) By virtue of their longer half-lives, their decay characteristics and fission yields are reasonably well known.
5.1.1 Differential Fission Product Decay Heat Measurements Since the main uncertainty regarding decay heating is at short cooling times, experiments have been performed for samples of pure fissionable isotopes irradiated for short periods. These irradiations are usually carried out in research reactors or using neutron beams. These systems allow measurements to be made at very short cooling times, down to a few seconds. Tobias reviewed the status of decay heating in 1980 [30]. Forty-five sets of decay heat measurements were compiled and analysed. The experimental data being reported from the 1940's to 1979. Tobias later updated this work for U235 and Pu239 [31]. The new work provides a simultaneous least squares fit to available beta, gamma and total decay heat measurements for each of U235 and Pu239. This analysis considered 54 sets of U235 measurements and 28 sets for Pu239 and took account of correlated uncertainties with a full covariance analysis. The experiments were performed mainly in France, USA, Germany and Japan. The Tobias results of the least-squares analysis were a set of decay heat functions following a single fission event. These functions can be directly compared with fission pulse calculations in FISPIN. The results used in this report are taken from Table 11 of reference 31. The use of the derived "single fission pulse" functions simplifies the analysis; only one FISPIN calculation is required for each fissioning system rather than a case for each individual experiment with its unique irradiation and cooling conditions. The other experimental results reported by Dickens et al [32] and Akiyama et al [33] used a similar method to produce a “single fission pulse” decay heat functions, but
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being based upon single sets of measurements have no independent verification of the data or the reported uncertainties. Figure 7 shows the results of FISPIN for the decay heat following a single U235 fission (modelled as 1010 fissions per second in 10-10 seconds). The FISPIN results using both JEF1 and JEF-2.2 are shown together with the results from Tobias. The figure shows the power in MeV/s per fission multiplied by cooling time (seconds) versus cooling time (seconds). By multiplying the power by the cooling time the range of the decay heat axis is reduced and the use of a logarithmic scale is avoided. Figure 8 shows similar results for Pu239, Figure 9 those for Pu239 and the results of Dickens, Figure 10 those for Pu241 and the results of Dickens, and Figure 11 those for U238 and the results of Akiyama. The decay heat calculations and experimental data generally show good agreement with some small deviations between 10 and 1000 seconds. To highlight the differences more clearly the ratio of the calculated results using JEF-2.2 to the experimental results of Tobias are shown in Figure 12 for U235 and Figure 13 for Pu239. The error bars shown are the one standard deviation uncertainties on the C/E ratio considering only the Tobias experimental uncertainties. Both show an under prediction of 5% between approximately 10 and 1000s, which is a little larger than the experimental error.
5.1.2 Integral Decay Heat Measurements Measurements of the decay heat of irradiated PWR assemblies have been performed in the USA. The data and comparisons with ORIGEN2 are reported by Schmittroth in reference 34. These data were compared to the predictions of FISPIN version 6 in reference 35. Reference 34 contains 24 measurements of decay heat, although some were of the same assembly with increasing decay times or using alternative methods (for four samples with inconsistent results). Table 39 contains the assembly information, the irradiation history and the measured decay power. As no detailed reactor information was available for the specified reactors, a PWR model developed for other parts of this work (Obrigheim) was used to generate cross-section libraries at enrichments of 2.6%, 3.4% and 4.0%. A series of FISPIN runs was produced modelling the assemblies in Table 39. The initial U234 and U236 content of fuel were determined as described in Appendix A. Impurities for LWR fuel were taken from reference 36. The structural materials (Zircaloy-4, Inconel-718 and stainless steel-304) for the three assemblies were taken from reference 34 and converted to an activation specification for FISPIN. It should be noted that to correctly model the activation of the structural materials a full 3D model would be necessary. However, as no route currently exists to correctly model a full 3D assembly within WIMS, it was assumed for this work that the structural materials could be modelled in the same way as fuel impurities. This will overestimate the flux seen by the end-pieces components of the assemblies. The experimental decay heat data and the FISPIN results are compared in Table 40 and Table 41 shows the breakdown of the decay heat between fission products, heavy elements, fuel impurities and structural materials. These results show good agreement between experiment and FISPIN. Neglecting the suspect results, the decay heat from those assemblies with Zircaloy clad fuel has only a small mean over-prediction (1.2%),
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whereas those with stainless steel clad fuel are over-predicted by a larger amount (4.8%). This larger over-prediction in the case of the stainless steel clad fuel may be due to over- predicting the heat produced in the end-pieces of the assembly (which contributes a greater fraction of the total than in the Zircaloy clad fuel) caused by using the flux in the fuel region.
5.2 Neutron Emission When irradiated spent fuel has been removed from a reactor, it will continue to generate neutrons directly from the radioactive decay (by spontaneous fission) of the nuclides present and indirectly from (alpha,n) reactions. The neutron emission is dependent upon the heavy elements present, which decay by spontaneous fission and generate alpha particles, and the light elements present, which when bombarded with alpha particles give rise to neutrons. The magnitude of the neutron emission will depend on the reactor system, fuel type, initial nuclide composition, the irradiation history and subsequent cooling.
5.2.1 Neutron Emission Measurements The results of measurements using the DIMPLE reactor of the neutron emission from four AGR irradiated fuel samples are reported in reference 37. After determining the neutron emission the samples were dissolved and analysed for various nuclides. The sample characteristics are given in Table 42. The irradiations of the samples were determined using the measured Nd148/U238 ratios (atom/atom) and FISPIN calculations. The mean on power rating was then determined using the on power days. Cross-section libraries produced as part of this work (section 3) were used and the neutron emission calculated using FISPIN. The results are shown in Table 43. FISPIN under predicts the neutron emission rate by approximately 20%. FISPIN predicts that between 90% and 95% of the neutron emission of these samples is a result of decays of Cm242 and Cm244. (Cm242 contributes approximately 10% and Cm244 approximately 80% of the neutron emission.) The calculated and measured values of these two nuclides are compared in Table 44 and show that the discrepancy in the prediction of the neutron emission rate can be attributed to the under-prediction of these nuclides.
6. Verification Another method of verifying the performance of an inventory code is to compare its results with those of another code and/or to use different nuclear data. Such verification has been performed by comparing the results of the WIMS-TRAIL-FISPIN route with those from two other routes: a) the reactor physics code CASMO4 [7] (JEF2.2 library), cross-section processing code CAS2FIS [8] (with library DB10TRAIL69), and FISPIN10 (with JEF2.2 decay files) and b) the SCALE4.4a processing package which includes the inventory code ORIGEN-S [9]. Table 45 lists the generic reactor types, initial enrichments and irradiations that are considered. The WIMS and FISPIN models were similar to those used in previous sections of this work, with the geometrical details and other parameters (enrichment, rating, etc.) modified appropriately. The fuel was irradiated continuously in both the
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WIMS and FISPIN models. The boron content of the water in Sizewell B was assumed to be 500ppm (by weight) and remain constant throughout the irradiation. The inventory, heat, gamma spectra and neutron source strengths were calculated after the periods of decay given in Table 46. The nuclides considered are listed in Table 1. The modelling routes through CASMO and SCALE were as similar as possible to that used in the WIMS models. They could not be identical because the codes use different input structures (especially in the method of defining the geometry). Magnox fuel was modelled using a pin cell in all three codes. The AGR model structures were different in each code. The PWR model structures were similar in WIMS and CASMO, but different in SCALE. Even though the structures may have been different, all material specifications, temperatures, dimensions, etc., were the same (although smearing may have been performed).
6.1 CASMO Comparison CASMO-4 is a multi-group two-dimensional transport theory code for burnup calculations on UOX and MOX fuels in BWR and PWR assemblies, or simple pin cells and cylindrical clusters of fuel rods. The code version used for the work in this paper was version 1.28.05H, which includes modifications to allow easy extraction of cross sections and neutron spectra required for producing a FISPIN cross section library. This version also includes options and routes developed to model Magnox and AGR fuel. CAS2FIS [8] is a post-processing utility that takes the data file produced by the above version of CASMO-4 and produces a FISPIN cross section library using both the burnup dependent cross sections produced by CASMO-4 and the cross sections from a TRAIL cross section library condensed using the burnup dependent neutron spectra produced by CASMO-4. The ratios of the results using the CASMO route to those using the WIMS route at shutdown are shown in Table 47 and at the maximum cooling times in Table 48. A summary giving the minimum and maximum values, the mean and standard deviation of the ratios over all the cooling times considered in shown in Table 49. Comparing the results at shutdown and at the maximum cooling times shows that the variation of the ratio with cooling time is small. At shutdown, the results for the fission products show that only 6 have a deviation of greater than 10% (these are Rb86, Ag108M, Ag110M, Ba133, Eu152 and Ta182), and none of these have a deviation greater than 20%. The deviations shown by the heavy nuclides are greater, but most are within 20%. U234 shows a deviation of approximately –50% in the all the high irradiation cases and several nuclides show a deviation of approximately +50% in the low irradiation cases for AGR fuel. These may be the cause of the +30% deviation in the neutron emission rate for these cases. For other fuel types and at longer cooling times the deviations in the neutron emission rate are smaller. The maximum deviation demonstrated by the decay heat predictions when considering all cooling times is +6%. The total gamma emission in both γ/s and MeV/s are within a few percent at all cooling times. Note, Hg203 is not predicted by FISPIN. The energy group structure of the gamma spectrum used by FISPIN is shown in Table 50. The ratio of CASMO to WIMS predictions of the gamma spectrum (γ/s) at shutdown is shown in Table 51. The results for the total, fission product and heavy nuclide spectra are shown separately. Table 52 gives the same results but at the longest cooling times
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considered. The differences at shutdown are small (less than 10%) for the total emission and fission products (the emission from fission products is dominating the total). The heavy nuclide results are worse especially at the higher irradiations. The differences in the total spectra at the longest cooling times are greater than those at shutdown, with some groups showing differences as large as 50%. This is because emission from heavy nuclides is dominating particular groups, and this shows greater differences than that from the fission products. When the spectra are compared in units of MeV/s, the ratios are almost identical to those obtained when comparing them in units of γ/s. Differences in the ratios are less than 2% at shutdown and 5% at the maximum cooling times.
6.2 SCALE Comparison SCALE is a code package consisting of many different modules, which perform many of the modelling tasks required in the nuclear industry. The module used in this work is called SAS2H. SAS2H performs one-dimensional neutron transport analyses of a reactor fuel assembly using a two-part procedure. The first part is a unit fuel-pin cell from which cell-weighted cross-sections are obtained. These feed into the second part which represents a larger unit cell (e.g. an assembly) within an infinite lattice. The flux spectrum obtained is used to determine the appropriate nuclide cross sections for use in a point- depletion computation (via ORIGEN-S) that produces the burnup-dependent fuel composition to be used in the next transport calculation step. SAS2H is used primarily to model PWRs and BWRs. Magnox fuel has been modelled as a pin cell by using only the first part of the two-part procedure and AGR fuel modelled by distributing pin cells on a triangular lattice. SCALE has not been validated for use in modelling the burnup of either Magnox or AGR fuel and there are no recommended routes for such calculations. The ratios of the results of using the SCALE route to those using the WIMS route at shutdown are shown in Table 53 and at the maximum cooling times in Table 54. A summary giving the minimum and maximum values, the mean and standard deviation of the ratios over all the cooling times considered in shown in Table 55. SCALE only provides output for those nuclides whose value exceeds a user-specified cut, but this can only be set to one of several values defined by the code. This unfortunately leads to the absence of many nuclides from the SCALE output. At shutdown, whilst the results of many nuclides show differences of less than 10%, the results for several fission products and heavy nuclides show large differences (greater than 50%). The variation of the ratios with cooling time is larger than that when comparing the results of the CASMO and WIMS routes. This is to be expected, since SCALE uses different decay data. The maximum deviation demonstrated by the decay heat predictions when considering all cooling times is +6%. The predictions of the neutron emission rate show the greatest deviations for AGR fuel, with a maximum of +74%. The total gamma emission in γ/s predicted by SCALE is larger by over a factor of four for some fuel types. The maximum deviation occurs after a few years cooling. The total gamma emission in MeV/s demonstrates smaller deviations, but sometimes varies by 50%. The energy group structure of the gamma spectrum used by SCALE is different to that used in FISPIN (Table 50). To enable a comparison to be made, the FISPIN results were grouped into the structure used by SCALE. However, it should be noted that SCALE uses
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different criteria to FISPIN when grouping gamma spectra. If the energy of a particular gamma line is E, then FISPIN will add its intensity to the contents of the group for which
≤ < El E Eu
where El and Eu are the energy of the lower boundary of the group and the upper boundary of the bin respectively. In SCALE, before adding to the contents of a group, the
intensity of a line of energy E is multiplied by E / Eav where Eav is the average (mid- − − − point) energy of the group. In addition, if E El or Eu E is less than 0.03(Eu El ) then one-half of the intensity is applied to each of the two groups having the boundary near the line. These procedures are claimed to give a better computation of dose rates in shielding calculations by conserving energy (which implies that the gamma spectrum expressed as γ/s is input to the shielding codes). The effect of multiplying the intensity by γ E / Eav is to introduce an error into the gamma spectrum (expressed as /s) whose
magnitude could at most be a factor of El / Eav too low or Eu / Eav too high (ignoring the effect of the “nearness” criterion). When comparing gamma spectra in terms of MeV/s, the adjustment to the intensity is not applicable, and will therefore not effect the results. However, the “nearness” criterion will have an effect. The ratio of SCALE to WIMS predictions of the gamma spectrum (γ/s) at shutdown is shown in Table 56. The results for the total, fission product and heavy nuclide spectra are shown separately. Table 57 gives the same results but at the longest cooling times considered. Only those groups for which both routes gave a non-zero value are shown; the SCALE results contained data in the highest energy groups but those of the WIMS/FISPIN route did not. The differences at shutdown are considerable for the total emission and fission products. The SCALE predictions for the low energy groups are higher (up to almost a factor of 5), but the ratio decreases rapidly as energy increases such that by the final energy group the SCALE prediction is only 20% that of the WIMS/FISPIN route. Extremely large differences are seen in the emission from heavy nuclides (up to several orders of magnitude) although they have no impact upon the total gamma emission. At the longest cooling times, the situation is complicated. Extremely large differences are present in the total, fission product, and heavy nuclide spectra. Some fission product groups show differences of 14 orders of magnitude, but have far less impact upon the total (and in some case, no impact at all). In order to shed some light upon the large discrepancies, the fission product results for group 12 of the Magnox 1GWd/t case at 100 years cooling were investigated. The ratio of SCALE to WIMS/FISPIN results is 4.07E14. SCALE predicts that the emission in this group is attributable to Y90. The amount of Y90 predicted by SCALE is within a few percent of that predicted by WIMS/FISPIN, however, JEF2.2 contains only one gamma line for Y90 and this does not fall within this group. A problem resulting from the grouping process itself can occur when comparing spectra - if in one decay library a particular gamma line falls into group 5, say, and in another it falls into group 6, its absence from group 5 may have little impact, but its inclusion in group 6 could result in a difference of orders of magnitude.
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When the spectra are compared in units of MeV/s, the ratios are all within 40% of their value obtained when comparing in units γ/s, except for the lowest energy group which was sometimes over twice as large.
7. Conclusion This report has compared the predictions of the WIMS8A-TRAIL1A-FISPIN10 calculational route with experimental measurements for Magnox, AGR and PWR fuel. The fuel types and ranges of parameters considered are given in Table 2. The mean and standard deviation of the results are summarised in Table 58 (heavy nuclides), Table 59 (fission products), and Table 60 (decay heat and neutron emission). In general, the results from the different fuel types show similar characteristics. In particular, U235 is over-predicted by on average approximately 5%. The magnitude of the over-prediction increases with irradiation, as shown in Figure 1. In order to reduce the effect of the different enrichment and irradiation ranges covered by the experiments, the calculated over experimental results for U235 are also shown as a function of U235 depletion in Figure 2. A small error in the burnout rate of U235 would be emphasised increasingly as the fraction of U235 lost increases. Pu239 is over-predicted by approximately 10%, the magnitude of which tends to increase with irradiation (Figure 3), although the over-prediction for Magnox fuel is particularly high. The over-prediction of Pu239 contributes to the over-prediction of plutonium, whose magnitude is approximately 5% and shows no discernible variation with irradiation (Figure 4). Since U235 and Pu239 contribute the majority of fissions, it is important that they are modelled accurately. Cm244 is usually under-predicted for all fuel types. For AGR and PWR fuel this is by an average of almost 20%, and there is no discernible variation with irradiation (Figure 5) For Magnox fuel the under-prediction is almost 50% on average, but the magnitude of the under-prediction decreases as irradiation increases. Eu154 was measured in a number of experiments and the results show that it is over- predicted, sometimes by as much as 100% (Figure 6). When modelling irradiated fuel samples, there are usually a number of parameters whose values must be assumed, or for which approximations are made. In addition, in both WIMS and FISPIN, the use of some keywords and the values of various computational parameters are at the discretion of the user. These factors can have an effect upon the results. Adjusting the value of a particular parameter may improve the result for one nuclide but could make that of another worse. For example, reducing the water temperature in a PWR results in the predicted amount of U235 and Pu239 going down. Since these are over-predicted, this would be a desirable result, however the prediction of Cm244 would also go down, which is already under-predicted. The predictions of decay heat have been compared to the measurements upon PWR assemblies. Results show a small over-prediction of up to 6%. The predictions of neutron emission rate have been compared to the measurements upon AGR samples. Results show an under-prediction of approximately 20%, which can be attributed to the under-prediction of Cm242 and Cm244.
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Of the nuclides listed in Table 1, only 27 have been analysed in the experiments considered in this work, and of these, 6 have been measured in one experiment only. Comparisons with other codes systems provide some indication of the validity of the nuclides for which no measurement data exist. This has been done in this report - the results of the WIMS8A-TRAIL1A-FISPIN10 route have been compared to those from two other routes: a) the reactor physics code CASMO4, cross-section processing code CAS2FIS, and FISPIN10 (using data libraries derived from JEF2.2) and b) the SCALE4.4a processing package which includes the inventory code ORIGEN-S (using data libraries derived predominantly from ENDF-B/V and ENDF-B/VI). Overall the agreement between the predictions of CASMO/FISPIN with those of WIMS/FISPIN is good, but there are some large differences at certain combinations of fuel parameters. In particular, U234 shows a deviation of approximately –50% in the all the high irradiation cases and several of the higher actinides show a deviation of approximately +50% in the low irradiation cases for AGR fuel. When using the SCALE route the predictions of many quantities are similar to those of the WIMS/FISPIN route, but there are several for which differences are large (over 50%). The differences in the gamma spectrum at the longest cooling times are very large indeed, with SCALE predicting over a thousand times more emission in some energy groups. It has been shown that some of the differences can be explained by differences in the gamma emission data used. It is important to note that that SCALE has not been validated for use in modelling the burnup of either Magnox or AGR fuel and there are no recommended routes for such calculations.
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8. References 1. Burstall R F, “FISPIN-A computer code for nuclide inventory calculations”, ND-R- 328 (R), October 1979. 2. Burstall R F and Wall S J, “Thermal Reactor Validation Work for the FISPIN Code”, AEA RS 1138, Issue 2, March 1994. 3. Little P, “Installation of the FISPIN Code Version 10.0.1”, BNFL Research and Technology, FISPDEV/01-02/rep/1, July 2001. 4. ANSWERS Software Service, “WIMS-A Modular Scheme for Neutronics Calculations. User Guide for Version 8”, AEAT, ANSWERS/WIMS(99)9, July 1999. 5. ANSWERS Software Service, “TRAIL-A Program to Generate Burnup-Dependent Cross Section Libraries for use in the Nuclide Inventory Code FISPIN Version 7. User Guide for Version 1A”, AEAT, ANSWERS/TRAIL/REPORT/001, May 2001. 6. OECD/NEA, “The JEF-2.2 Nuclear Data Library”, JEFF Report 17, ISBN 92-64-17686-1. Available from the OECD Nuclear Energy Agency, Le Seine Saint-Germain, 12 Boulevard des Îles, F-92130, Issy-les-Moulineaux, France. 7. Edenius M, et al, “CASMO-4, A Fuel Assembly Burnup Program: User’s Manual”, STUDVISK/SOA-95/1, 1995. 8. Mills R W, “CAS2FIS: A User Guide and Physics Manual”, BNFL RDR1420, 18 May 1998. 9. SCALE, “SCALE: A Modular Code System for Performing Standardised Computer Analyses for Licensing Evaluation”, NUREG/CR-0200, Rev. 6, (ORNL/NUREG/CSD-2R6), Vols. I, II, and III (May 2000). Version 4.4a of the code package is available from Radiation Safety Information Computational Centre at Oak Ridge National Laboratory as CCC545. (www.cped.ornl /scale), 10. Nichols A L, Dean C J, Neill A P, “Extension and Maintenance of Evaluated Decay Data Files: UKPADD-6”, AEAT-5226, March 1999. 11. CRC Handbook of Chemistry and Physics, 78th Edition, 1997-1998, CRC Press, Boca Raton, FL, 1997. 12. Alldred B, “The abundance of U-234 and U-236 in Unirradiated Fuel”, BNFL Research and Development Department RM577. Also NAMAG/P(87)13, IMAC/(P86)145, 1988. 13. Nair S, “Magnox Fuel Inventories : Experiment and Calculation Using a Point Source Model”, CEGB RD/B/N4349, August 1978. 14. Foster E, Fudge AJ, Glover KM, “Analysis of Irradiated Magnox Fuel For Fission Product and Actinide Elements”, AERE Harwell, AERE-R9212, March 1980. 15. Varley GA, “A Review of the ARGOSY 4MC Route for Predicting Plutonium and Uranium Concentrations in Irradiated Magnox Fuel”, BNFL. 16. Edens, DJ, BNFL, Private Communications, BNFL/NDCPEXT/00-01/1/in/55 and BNFL/NDCPEXT/00-01/1/in/56.
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17. Tobias A and Whittaker A, “A Summary of Isotopic Analysis of CAGR Fuel Samples”, RSWG/P(88)29, 1988. 18. Martin J, British Energy, Private Communication, BNFL/NDCPEXT/00-01/1/in/40. 19. Barbero P, et al, “Post Irradiation Analysis of the Obrigheim PWR Spent Fuel”, EUR 6589 EN, 1980. 20. Guardini S and Guzzi S, “Bench Mark Report Relevant to Gundremmingen and Obrigheim Reactors”, EUR COMM 3703, 1980. 21. Guardini S and Guzzi S, “Benchmark Reference Data on Post Irradiation Analysis of Light Water Reactor Fuel Samples”, EUR 7979 EN, 1983. 22. Alldred B and Quayle GA, “Validation of the FISPIN Code Version 6 for PWR Calculations”, IMAC/P(88)172. 23. Evans RF, Little P, Mills RW, “The Comparison of FISPIN inventories with experimental results for the Obrigheim Pressurised Water Reactor for UO2 fuel”, BNFL RDR 1528, 19 November 1998. 24. Guenther R J et al, “Characterization of Spent fuel Approved Testing Material ATM-103”, PNL-5109-103, April 1988. 25. Guenther R J et al, “Characterization of Spent fuel Approved Testing Material ATM-104”, PNL-5109-104, December 1991. 26. Guenther R J et al, “Characterization of Spent fuel Approved Testing Material ATM-106”, PNL-5109-106, October 1988. 27. Hermann O W et al, “Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analyses”, ORNL/TM-12667, March 1995. 28. Boulanger D and Lippens M, “ARIANE International Program, Final Report”, AR 2000/15, BELGONUCLEAIRE, December 2000. (Proprietary information) 29. Aoust T, “ARIANE International Program, Irradiation Data Report Part 1”, AR 99/13, BELGONUCLEAIRE, July 1999. Aoust T, “ARIANE International Program, Irradiation Data Report Part 2”, AR 99/13, BELGONUCLEAIRE, July 1999. Aoust T, “ARIANE International Program, Irradiation Data Report Part 3”, AR 99/13, BELGONUCLEAIRE, July 1999. (All proprietary information) 30. Tobias A, "Decay Heat", Progress in Nuclear Energy, Vol.5, No. 1, pp.1-193 (1980). 31. Tobias A, "Derivation of Decay Heat Benchmarks for U235 and Pu239 by a Least Squares Fit to Measured Data", CEGB report RD/B/6210/R89 (1989) and committee paper DIDSG/P(88)388. 32. Dickens J K, Love T A and McConnell J W, "Fission-Product Energy release for times following thermal-neutron fission of plutonium-239 and plutonium-241 between 2 and 14000 seconds", Nuclear Science and Engineering, Vol. 78, pp. 126- 146 (1981). 33. Akiyama M et al, "Proceedings of a Conference on Nuclear Data for Basic and Applied Physics", Sante Fe, USA (1985).
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34. Schmittroth F, "ORIGEN2 Calculations of PWR spent fuel decay heat compare with calorimeter data." HEDL-TME 83-32 UC-85 35. Alldred B and Quayle G A, "Validation of the FSIPIN code version 6 for calculations of heat from PWR fuel elements". BNFL Research and Development Department RM588. Also NAMAG/P(87)59, RSWG/P(88)8, IMAC/P(88)172 and DIDSG(86)(/340). 36. Croff A G, et al, “Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code”, ORNL/TM-6051, September 1978. 37. Gulliford N T, "Measurement of Neutron Source Strengths in Irradiated CAGR Fuel Samples in DIMPLE", AEEW-R2532.
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Appendix A: FISPIN and WIMS Parameters
A1. Introduction In this Appendix, the values of a number of the parameters which must be specified in WIMS and/or FISPIN are discussed. It is not intended as an exhaustive list of such parameters.
A2. Irradiation History When modelling the irradiation history of a sample in FISPIN, the time on-power and the length of shutdowns is usually known, together with the final irradiation. What is not usually reported is the fraction of the final irradiation attained in each on-power cycle by the sample. Instead, that attained by the rod, or the assembly, or the reactor the sample was contained within is reported. Thus, the rating to use for each on-power cycle is not known. An approximation can be obtained by assuming a sample attains the same fraction of its final irradiation in each on-power period as the rod/assembly/reactor it is within. If Ii is the irradiation of the rod/assembly/reactor for the ith s on-power period, then the sample’s irradiation, Ii , is given by
I I s = i F s i F i where F is the final irradiation of the rod/assembly/reactor and F s that of the sample. Assuming s that the rating is constant during an on-power period, the sample rating for the ith period, Ri , is given by
s s = Ii Ri di I = i F s di F R = i F s F
where Ri is the rod/assembly/reactor rating for period i and di is the duration of period i. It is assumed that the best approximation to the sample’s irradiation history is obtained when using that of the rod in the above formulae, that of the assembly giving the next best approximation, and that of the reactor giving the least accurate.
A3. INTE and LEVEL Parameters The INTE keyword was always used. The first parameter of the LEVEL keyword was set to 20 and the second parameter was chosen according to the following formula:
= L2i MAX(8, NINT(I i ))
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where L2i is the value if the second LEVEL parameter for the on-power period i, I i is the irradiation of period i (in GWd/t), NINT rounds to the nearest integer and MAX selects the maximum value. Thus, for irradiation periods of less than or equal to 8 GWd/t the second LEVEL parameter is set to 8, above this it is set to a greater value such that the spacing of calculational steps of FISPIN is 1 GWd/t.
A4. Initial U234 and U236 Content of Fuel The U234 content of natural uranium (as used in Magnox reactors) was 5.5E-3% (by atom) [11]. Methods of deriving the abundance of U234 and U236 in AGR and PWR fuel were obtained from reference 12. The U234 content of AGR and PWR fuel was derived from the U235 enrichment. For AGR fuel the following formula was used:
= − W4 (1.1576W5 0.3914) 100
where W4 is the percentage by weight of U234 with respect to total uranium, and W5 is the percentage by weight of U235 (i.e. the U235 enrichment). This formula was derived by fitting the results of the mass spectrometric analysis of a large number of fuel batches at the BNFL Springfields fuel manufacturing plant. Similarly, for PWR fuel the U234 content was determined using:
= − W4 (1.036W5 0.449) 100
This formula was obtained from Westinghouse and was based upon analytical data for their PWR fuel. The U236 content of AGR fuel was assumed to be 290ppm (by weight). This was the median value determined in the study of the AGR fuel produced at Springfields. For PWR fuel a nominal value of 150ppm (by weight) was used. In the case of Goesgen fuel, its isotopic composition was specified and so this was used instead of the above assumptions.
A5. Rating Used in the WIMS Runs The rating used in the WIMS runs is often different from, or an average of, the ratings experienced by a sample during irradiation. The effect of this upon the results of FISPIN is negligible.
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Appendix B: Tables
Table 1: Nuclides of interest.1
Nuclide Half-life Nuclide Half-life Nuclide Half-life H3 12.33 y Sb124 60.20 d Ba133 10.52 y Br84 31.80 m Sb125 2.73 y Ba139 1.38 h Kr83M 1.83 h Sb128 9.01 h Ba140 12.74 d Kr85 10.72 y Sb128M 10.40 m Ba141 18.27 m Kr85M 4.48 h Sb129 4.40 h La140 1.68 d Kr87 1.27 h Sb130M 6.30 m La141 3.93 h Kr88 2.84 h Sb131 23.00 m La142 1.52 h Kr89 3.17 m Te131 25.00 m Ce143 1.38 d Rb86 18.66 d Te132 3.26 d Ce144/Pr144 284.90 d Rb88 17.80 m Te133 12.50 m Pr146 24.15 m Rb89 15.15 m Te134 41.83 m Pm147 2.62 y Rb90 2.55 m I127 stable Pm148 5.37 d Rb91 58.40 s I129 1.569E+7 y Pm148M 41.28 d Sr89 50.50 d I130 12.36 h Pm150 2.68 h Sr90/Y90 29.12 y I131 8.04 d Pm154 1.70 m Sr91 9.52 h I132 2.30 h Eu152 13.32 y Sr92 2.71 h I133 20.80 h Eu154 8.60 y Y92 3.54 h I134 52.60 m Eu155 4.96 y Y93 10.10 h I135 6.61 h Eu156 15.19 d Y94 19.10 m I136 1.40 m Ta182 115.00 d Zr95 63.98 d Xe131M 11.90 d Hg203 46.59 d Zr97 16.90 h Xe133 5.25 d U234 2.457E+5 y Nb94 2.030E+4 y Xe133M 2.19 d U235 7.038E+8 y Nb95 35.15 d Xe135 9.09 h U236 2.342E+7 y Nb97 1.20 h Xe135M 15.65 m U238 4.468E+9 y Nb97M 60.00 s Xe137 3.82 m Np239 2.35 d Mo101 14.60 m Xe138 14.17 m Pu238 87.70 y Tc104 18.40 m Cs133 stable Pu239 2.411E+4 y Ru103 39.35 d Cs134 2.06 y Pu240 6.563E+3 y Ru105 4.44 h Cs135 2.298E+6 y Pu241 14.40 y Ru106/Rh106 1.01 y Cs136 13.16 d Am241 4.327E+2 y Ag108M 4.180E+2 y Cs137/Ba137M 30.00 y Am243 7.365E+3 y Ag110M 249.90 d Cs138 32.20 m Cm242 162.94 d Sn127 2.10 h Cs139 9.27 m Cm243 30.00 y Cs140 1.06 m Cm244 18.10 y
1 For a pair of nuclides in equilibrium (such as Sr90/Y90), the half-life of the parent is shown. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 33 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 2: Fuel types and the ranges of parameters considered in this paper.
Reactor Type Enrichment Irradiation Rating % GWd/t MW/t Nuclide Inventory Magnox natural 3-9 1.5-3.6 AGR 1.542-2.55 1-26 5.4-15.5 PWR (Obrigheim) 2.83-3 16-37 15.9-37.0 PWR (Calvert Cliffs) 2.453-3.038 13-47 11.4-29.6 PWR (Goesgen) 3.5-4.1 31-59 30.0-50.4 PWR (Combined) 2.453-4.1 13-59 11.4-50.4
Decay Heat PWR 2.556-4.005 26-39 17.8-33.4
Neutron Emission AGR 2.01-2.55 19-22 16.5-18.4
Table 3: Irradiation parameters for the Magnox samples.2
Sample On-power Elapsed Element irradiation Sample irradiation Rating time time quoted by station derived from Nd148/U (MW/t) (d) (d) (MWd/t) (MWd/t) A 2133 2398 3900 ± 400 3271 1.5335 B 2167 2412 7000 ± 700 6576 3.0346 C 1934 2282 7000 ± 700 6902 3.5688 D 3745 4500 9400 ± 900 8932 2.4329 for 6552MWd/t, 2.2626 for 2380MWd/t
Table 4: Cooling times for the Magnox samples.
Sample Discharge date3 Measurement date Cooling (d) Fission Products Actinides4 Fission Products Actinides A 27/8/1976 11/5/1977 20/4/1977 257 236 B 24/8/1976 11/5/1977 27//4/1977 260 246 C 20/11/1975 1/10/1976 2/2/1977 316 440 D 5/1/1975 1/10/1976 1/2/1977 635 758
2 Refer to the text for the source or derivation of these values. 3 From reference 13 for A and B (date for B was corrected), derived from dates in reference 2 for C and D. 4 From reference 14. Measurement dates are given for alpha spectrometry only, assumed to apply to mass spectrometry results also. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 34 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 5: Magnox results.5
Sample A B C D Nuclide C E C/E C E C/E C E C/E C E C/E Mean ; SD U234/U (1E-2 a/a) 0.004957 0.006 +/- 0.002 0.83 +/- 0.28 0.004471 0.005 +/- 0.002 0.89 +/- 0.36 0.86 ; 0.05 U235/U (1E-2 a/a) 0.4491 0.455 +/- 0.010 0.99 +/- 0.02 0.2832 0.286 +/- 0.010 0.99 +/- 0.03 0.2705 0.27 +/- 0.01 1.00 +/- 0.04 0.2106 0.20 +/- 0.01 1.05 +/- 0.05 1.01 ; 0.03 U236/U (1E-2 a/a) 0.04234 0.044 +/- 0.005 0.96 +/- 0.11 0.06770 0.070 +/- 0.005 0.97 +/- 0.07 0.06961 0.08 +/- 0.01 0.87 +/- 0.11 0.07911 0.08 +/- 0.01 0.99 +/- 0.12 0.95 ; 0.05 U238/U (1E-2 a/a) 99.50 99.495 +/- 0.19 1.00 +/- 0.00 99.64 99.639 +/- 0.19 1.00 +/- 0.00 99.66 99.65 +/- 0.19 1.00 +/- 0.00 99.71 99.71 +/- 0.19 1.00 +/- 0.00 1.00004 ; 0.00006 Pu238/Pu (1E-2 a/a) 0.07418 0.15 +/- 0.01 0.49 +/- 0.03 0.2382 0.36 +/- 0.01 0.66 +/- 0.02 0.2537 0.35 +/- 0.02 0.72 +/- 0.04 0.5662 0.75 +/- 0.03 0.75 +/- 0.03 0.66 ; 0.12 Pu239/Pu (1E-2 a/a) 80.42 76.37 +/- 0.14 1.05 +/- 0.00 67.01 60.68 +/- 0.12 1.10 +/- 0.00 66.06 60.75 +/- 0.12 1.09 +/- 0.00 61.04 56.91 +/- 0.11 1.07 +/- 0.00 1.08 ; 0.02 Pu240/Pu (1E-2 a/a) 16.73 19.72 +/- 0.09 0.85 +/- 0.00 26.51 30.98 +/- 0.06 0.86 +/- 0.00 27.23 30.92 +/- 0.06 0.88 +/- 0.00 30.39 33.13 +/- 0.07 0.92 +/- 0.00 0.88 ; 0.03 Pu241/Pu (1E-2 a/a) 2.500 3.33 +/- 0.03 0.75 +/- 0.01 5.048 6.17 +/- 0.03 0.82 +/- 0.00 5.141 6.12 +/- 0.03 0.84 +/- 0.00 5.896 6.42 +/- 0.03 0.92 +/- 0.00 0.83 ; 0.07 Pu242/Pu (1E-2 a/a) 0.2726 0.43 +/- 0.01 0.63 +/- 0.01 1.192 1.81 +/- 0.02 0.66 +/- 0.01 1.315 1.87 +/- 0.02 0.70 +/- 0.01 2.100 2.80 +/- 0.03 0.75 +/- 0.01 0.69 ; 0.05 Pu/U (1E-3 g/g) 2.188 2.11 +/- 0.02 1.04 +/- 0.01 3.515 3.35 +/- 0.03 1.05 +/- 0.01 3.628 3.35 +/- 0.03 1.08 +/- 0.01 4.385 4.04 +/- 0.04 1.09 +/- 0.01 1.06 ; 0.02 Nd142/U (1E-6 g/g) 0.5315 0.71 +/- 0.01 0.75 +/- 0.01 2.101 2.17 +/- 0.02 0.97 +/- 0.01 2.306 3 +/- 0.03 0.77 +/- 0.01 3.882 5 +/- 0.05 0.78 +/- 0.01 0.82 ; 0.10 Nd143/U (1E-6 g/g) 103.4 102.4 +/- 1.0 1.01 +/- 0.01 179.3 176.1 +/- 1.8 1.02 +/- 0.01 186.3 182 +/- 1.8 1.02 +/- 0.01 222.1 217 +/- 2.0 1.02 +/- 0.01 1.02 ; 0.01 Nd144/U (1E-6 g/g) 106.2 106.0 +/- 1.0 1.00 +/- 0.01 225.9 226.4 +/- 2.3 1.00 +/- 0.01 240.1 242 +/- 2.4 0.99 +/- 0.01 332.5 348 +/- 3.0 0.96 +/- 0.01 0.99 ; 0.02 Nd145/U (1E-6 g/g) 76.04 76.3 +/- 0.7 1.00 +/- 0.01 145.1 145.1 +/- 1.5 1.00 +/- 0.01 151.7 153 +/- 1.5 0.99 +/- 0.01 190.4 182 +/- 3.0 1.05 +/- 0.02 1.01 ; 0.03 Nd146/U (1E-6 g/g) 62.71 63.6 +/- 0.6 0.99 +/- 0.01 126.7 127.8 +/- 1.3 0.99 +/- 0.01 133.2 135 +/- 1.4 0.99 +/- 0.01 173.6 177 +/- 1.8 0.98 +/- 0.01 0.986 ; 0.005 Nd148/U (1E-6 g/g) 36.76 36.9 +/- 0.4 1.00 +/- 0.01 74.21 74.3 +/- 0.7 1.00 +/- 0.01 77.98 78 +/- 0.8 1.00 +/- 0.01 100.8 101 +/- 1.0 1.00 +/- 0.01 0.998 ; 0.001 Nd150/U (1E-6 g/g) 16.81 17.3 +/- 0.2 0.97 +/- 0.01 35.77 36.6 +/- 0.4 0.98 +/- 0.01 37.70 38 +/- 0.4 0.99 +/- 0.01 50.28 51 +/- 0.5 0.99 +/- 0.01 0.98 ; 0.01 Pu238/U (1E-6 g/g) 1.615 2.6 +/- 0.06 0.62 +/- 0.01 8.325 12.3 +/- 0.2 0.68 +/- 0.01 9.152 11.7 +/- 0.3 0.78 +/- 0.02 24.68 28.8 +/- 0.7 0.86 +/- 0.02 0.73 ; 0.11 Am241/U (1E-6 g/g) 6.766 8.8 +/- 0.2 0.77 +/- 0.02 21.60 21.1 +/- 0.5 1.02 +/- 0.02 27.13 31.4 +/- 1.0 0.86 +/- 0.03 72.16 76.4 +/- 2.7 0.94 +/- 0.03 0.90 ; 0.11 Am243/U (1E-6 g/g) 2.399 4 +/- 2 0.60 +/- 0.30 8.297 8 +/- 4 1.04 +/- 0.52 0.82 ; 0.31 Cm242/U (1E-7 g/g) 0.7757 1.51 +/- 0.03 0.51 +/- 0.01 4.773 7.32 +/- 0.08 0.65 +/- 0.01 2.094 3.40 +/- 0.09 0.62 +/- 0.02 1.250 1.57 +/- 0.03 0.80 +/- 0.02 0.64 ; 0.12 Cm244/U (1E-8 g/g) 0.6043 1.9 +/- 0.4 0.32 +/- 0.07 19.25 37.1 +/- 0.7 0.52 +/- 0.01 23.78 45 +/- 2 0.53 +/- 0.02 93.63 121 +/- 3 0.77 +/- 0.02 0.53 ; 0.19 Cs134/Cs137 (Bq/Bq) 0.1687 0.161 1.05 0.3285 0.294 1.12 0.3337 0.417 0.80 0.2464 0.235 1.05 1.00 ; 0.14 Cs137/U (1E+8 Bq/g) 3.659 3.48 +/- 0.2 1.05 +/- 0.06 7.376 5.92 +/- 0.25 1.25 +/- 0.05 7.760 7.57 +/- 0.37 1.03 +/- 0.05 9.198 8.78 +/- 0.44 1.05 +/- 0.05 1.09 ; 0.10 Pr144/U (1E+9 Bq/g) 1.104 1.33 +/- 0.05 0.83 +/- 0.03 2.037 2.03 +/- 0.1 1.00 +/- 0.05 1.920 1.90 +/- 0.10 1.01 +/- 0.05 0.5526 0.549 +/- 0.028 1.01 +/- 0.05 0.96 ; 0.09 Ce144/U (1E+9 Bq/g) 1.104 1.45 +/- 0.05 0.76 +/- 0.03 2.037 2.04 +/- 0.01 1.00 +/- 0.00 1.920 1.88 +/- 0.09 1.02 +/- 0.05 0.5526 0.544 +/- 0.027 1.02 +/- 0.05 0.95 ; 0.13 Zr95/U (1E+8 Bq/g) 1.658 2.04 +/- 0.1 0.81 +/- 0.04 2.992 3.09 +/- 0.15 0.97 +/- 0.05 1.554 1.92 +/- 0.1 0.81 +/- 0.04 0.03595 0.052 +/- 0.001 0.69 +/- 0.01 0.82 ; 0.11 Nb95/U (1E+8 Bq/g) 3.471 1.79 +/- 0.1 1.94 +/- 0.11 6.272 2.36 +/- 0.1 2.66 +/- 0.11 3.328 1.71 +/- 0.2 1.95 +/- 0.23 0.07958 0.0403 +/- 0.002 1.97 +/- 0.10 2.13 ; 0.35 Cs134/U (1E+8 Bq/g) 0.6171 0.560 +/- 0.032 1.10 +/- 0.06 2.423 1.74 +/- 0.07 1.39 +/- 0.06 2.589 3.16 +/- 0.15 0.82 +/- 0.04 2.266 2.06 +/- 0.10 1.10 +/- 0.06 1.10 ; 0.23 Pu238/U (1E-5 g/g) 0.1615 0.315 0.51 0.8325 1.20 0.69 0.9152 1.17 0.79 2.468 3.01 0.82 0.70 ; 0.14 Pu239/U (1E-3 g/g) 1.758 1.61 1.09 2.352 2.03 1.16 2.393 2.03 1.18 2.672 2.29 1.16 1.15 ; 0.04 Pu240/U (1E-3 g/g) 0.3674 0.417 0.88 0.9344 1.04 0.90 0.9903 1.04 0.95 1.336 1.34 1.00 0.93 ; 0.05 Pu241/U (1E-4 g/g) 0.5513 0.708 0.78 1.787 2.08 0.86 1.878 2.06 0.91 2.602 2.61 1.00 0.89 ; 0.09 Pu242/U (1E-5 g/g) 0.6035 0.918 0.66 4.236 6.13 0.69 4.822 6.33 0.76 9.305 11.4 0.81 0.73 ; 0.07
5 Values of those entities in italics are derived in this work from other measurements. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 35 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 6: Characteristics and reactor parameters of the AGR samples.
PIE Ref. No / Reactor Channel Element Element Pellet Pin Ring Pellet Laboratory Load Date First Power Date6 Shutdown Discharge Enrichment Element Sample PIST8 Elapsed On-Power Mean Sample Position Design Bore Date Date (U235 % g/g) Irradiation Irradiation7 Time9 Time10 On-Power number (d) 11 (Stage) (inch) (MWd/t) (MWd/t) (d) (d) Rating (MW/t) B4001/1 Hinkley R4 U37 3 1 0.2 1+3+5 inner 41 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1100 200 237 204 5.392 B4001/2 Hinkley R4 U37 3 1 0.2 8+11+15 middle 41 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1243 200 237 204 6.091 B4001/3 Hinkley R4 U37 3 1 0.2 21+25+31+35 outer 41 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1415 200 237 204 6.935 B4001/4 Hinkley R4 U37 3 1 0.2 1+3+5 inner 64 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1391 200 237 204 6.817 B4001/5 Hinkley R4 U37 3 1 0.2 8+11+15 middle 64 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1507 200 237 204 7.386 B4001/6 Hinkley R4 U37 3 1 0.2 21+25+31+35 outer 64 Harwell 15/01/1976 01/02/76 00:57:36 25/09/1976 2.012 1197 1618 200 237 204 7.930 B4040/1 Hinkley R4 Q11 3 1 0.2 2+4+6 inner 41 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 6086 826 1314 774 7.863 B4040/2 Hinkley R4 Q11 3 1 0.2 7+11+15 middle 41 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 6182 826 1314 774 7.988 B4040/3 Hinkley R4 Q11 3 1 0.2 19+25+31 outer 41 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 7035 826 1314 774 9.089 B4040/4 Hinkley R4 Q11 3 1 0.2 2+4+6 inner 42 Winfrith 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 5923 826 1314 774 7.653 B4040/5 Hinkley R4 Q11 3 1 0.2 7+11+15 middle 42 Winfrith 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 6280 826 1314 774 8.114 B4040/6 Hinkley R4 Q11 3 1 0.2 19+25+31 outer 42 Winfrith 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 7214 826 1314 774 9.321 B4040/7 Hinkley R4 Q11 3 1 0.2 2+4+6 inner 64 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 7002 826 1314 774 9.047 B4040/8 Hinkley R4 Q11 3 1 0.2 7+11+15 middle 64 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 7317 826 1314 774 9.453 B4040/9 Hinkley R4 Q11 3 1 0.2 19+25+31 outer 64 Harwell 29/04/1974 01/02/76 00:57:36 07/09/1979 12/09/1979 1.542 6671 7851 826 1314 774 10.143 B3065/1 Hinkley R3 W27 4 1 0.2 1+3+5 inner 19 Winfrith 07/03/1976 24/09/76 09:21:36 25/07/1980 08/07/1980 2.012 9465 7785 384 1400 928 8.389 B3065/2 Hinkley R3 W27 4 1 0.2 7+11+15 middle 19 Winfrith 07/03/1976 24/09/76 09:21:36 25/07/1980 08/07/1980 2.012 9465 8466 384 1400 928 9.123 B3065/3 Hinkley R3 W27 4 1 0.2 19+25+31 outer 19 Winfrith 07/03/1976 24/09/76 09:21:36 25/07/1980 08/07/1980 2.012 9465 9630 384 1400 928 10.377 B3086/1 Hinkley R3 E33 4 1 0.2 1+4 inner 11 Harwell 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 10264 385 1597 1125 9.124 B3086/2 Hinkley R3 E33 4 1 0.2 7+13 middle 11 Harwell 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 10925 385 1597 1125 9.711 B3086/3 Hinkley R3 E33 4 1 0.2 19+28 outer 11 Harwell 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 12242 385 1597 1125 10.882 B3086/4 Hinkley R3 E33 4 1 0.2 1+4 inner 12 Winfrith 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 9875 385 1597 1125 8.778 B3086/5 Hinkley R3 E33 4 1 0.2 7+13 middle 12 Winfrith 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 10579 385 1597 1125 9.404 B3086/6 Hinkley R3 E33 4 1 0.2 19+28 outer 12 Winfrith 06/03/1976 24/09/76 09:21:36 07/02/1981 21/02/1981 2.012 11202 11811 385 1597 1125 10.499 C3139/1 Hunterston R3 1084 4 1 0.2 1+3+5 inner 11 Harwell 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 13487 628 2306 1593 8.467 C3139/2 Hunterston R3 1084 4 1 0.2 7+11+15 middle 11 Harwell 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 14339 628 2306 1593 9.001 C3139/3 Hunterston R3 1084 4 1 0.2 19+25+31 outer 11 Harwell 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 16273 628 2306 1593 10.216
6 For all bar B4259, this is the date of the first power of the reactor. For B4259, this is the start date of the next on-power period. 7 Derived in this work from the measured Nd148/U mass ratio and FISPIN. 8 A nominal period of half a year plus the difference between first power and load dates. 9 The length of time from first power to shutdown. 10 The on-power time was calculated from a simplified irradiation history. 11 The rating was derived from the sample irradiation and time on power. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 36 of 115 RAT 1972 Issue 02 RAWG/P(01)04
PIE Ref. No / Reactor Channel Element Element Pellet Pin Ring Pellet Laboratory Load Date First Power Date6 Shutdown Discharge Enrichment Element Sample PIST8 Elapsed On-Power Mean Sample Position Design Bore Date Date (U235 % g/g) Irradiation Irradiation7 Time9 Time10 On-Power number (d) 11 (Stage) (inch) (MWd/t) (MWd/t) (d) (d) Rating (MW/t) C3139/4 Hunterston R3 1084 4 1 0.2 1+3+5 inner 12 Winfrith 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 13503 628 2306 1593 8.477 C3139/5 Hunterston R3 1084 4 1 0.2 7+11+15 middle 12 Winfrith 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 13599 628 2306 1593 8.537 C3139/6 Hunterston R3 1084 4 1 0.2 19+25+31 outer 12 Winfrith 12/11/1974 31/01/76 00:00:00 25/05/1982 28/05/1982 2.012 15243 16299 628 2306 1593 10.232 B4175/1 Hinkley R4 N41 4 1 0.2 1+3+5 inner 11 Harwell 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 16267 246 2597 1924 8.455 B4175/2 Hinkley R4 N41 4 1 0.2 7+11+15 middle 11 Harwell 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 17312 246 2597 1924 8.998 B4175/3 Hinkley R4 N41 4 1 0.2 19+25+31 outer 11 Harwell 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 19591 246 2597 1924 10.183 B4175/4 Hinkley R4 N41 4 1 0.2 1+3+5 inner 12 Winfrith 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 15865 246 2597 1924 8.246 B4175/5 Hinkley R4 N41 4 1 0.2 7+11+15 middle 12 Winfrith 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 17260 246 2597 1924 8.971 B4175/6 Hinkley R4 N41 4 1 0.2 19+25+31 outer 12 Winfrith 30/11/1975 01/02/76 00:57:36 13/03/1983 2.012 19074 19677 246 2597 1924 10.227 B4180/1 Hinkley R4 V35 4 2 0.2 19 outer 12-15 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 15921 17544 183 2121 1596 10.992 B4180/2 Hinkley R4 V35 5 2 0.2 19 outer 12-15 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 15507 16688 183 2121 1596 10.456 B4180/3 Hinkley R4 V35 6 2 0.2 19 outer 12-15 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 14352 16430 183 2121 1596 10.294 B4180/4 Hinkley R4 V35 4 2 0.2 19 outer 32-35 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 15921 17200 183 2121 1596 10.777 B4180/5 Hinkley R4 V35 5 2 0.2 19 outer 32-35 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 15507 16774 183 2121 1596 10.510 B4180/6 Hinkley R4 V35 6 2 0.2 19 outer 32-35 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 14352 15570 183 2121 1596 9.756 B4180/7 Hinkley R4 V35 4 2 0.2 29 outer 32-35 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 15921 16086 183 2121 1596 10.079 B4180/8 Hinkley R4 V35 6 2 0.2 29 outer 32-35 Harwell 20/05/1977 11/03/1983 09/05/1983 2.50 14352 14537 183 2121 1596 9.108 B4181/1 Hinkley R4 E13 5 2 0.2 29 outer 13 Harwell 30/04/1977 11/03/1983 05/05/1983 2.50 16024 16002 183 2141 1616 9.902 B4181/2 Hinkley R4 E13 5 2 0.2 29 outer 14 Harwell 30/04/1977 11/03/1983 05/05/1983 2.50 16024 16517 183 2141 1616 10.221 B4181/3 Hinkley R4 E13 5 2 0.2 29 outer 33 Harwell 30/04/1977 11/03/1983 05/05/1983 2.50 16024 15916 183 2141 1616 9.849 B4181/4 Hinkley R4 E13 5 2 0.2 29 outer 34 Harwell 30/04/1977 11/03/1983 05/05/1983 2.50 16024 16089 183 2141 1616 9.956 B3221/1 Hinkley R3 S13 4 2 0.25 2+4+6 inner 11 Harwell 27/05/1979 29/01/1984 2.17 21225 17954 183 1708 1503 11.945 B3221/2 Hinkley R3 S13 4 2 0.25 8+12+16 middle 11 Harwell 27/05/1979 29/01/1984 2.17 21225 19165 183 1708 1503 12.751 B3221/3 Hinkley R3 S13 4 2 0.25 22+28+34 outer 11 Harwell 27/05/1979 29/01/1984 2.17 21225 21254 183 1708 1503 14.141 B3221/4 Hinkley R3 S13 4 2 0.25 2+4+6 inner 12 Winfrith 27/05/1979 29/01/1984 2.17 21225 17698 183 1708 1503 11.775 B3221/5 Hinkley R3 S13 4 2 0.25 8+12+16 middle 12 Winfrith 27/05/1979 29/01/1984 2.17 21225 18488 183 1708 1503 12.301 B3221/6 Hinkley R3 S13 4 2 0.25 22+28+34 outer 12 Winfrith 27/05/1979 29/01/1984 2.17 21225 20748 183 1708 1503 13.804 B4259/1 Hinkley R4 S21 4 2 0.25 1+3+5 inner 11 Harwell 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 19061 187 1908 1709 11.153 B4259/2 Hinkley R4 S21 4 2 0.25 7+11+15 middle 11 Harwell 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 20106 187 1908 1709 11.765 B4259/3 Hinkley R4 S21 4 2 0.25 19+25+31 outer 11 Harwell 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 22446 187 1908 1709 13.134 B4259/4 Hinkley R4 S21 4 2 0.25 1+3+5 inner 11 Winfrith 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 19146 187 1908 1709 11.203 B4259/5 Hinkley R4 S21 4 2 0.25 7+11+15 middle 11 Winfrith 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 20273 187 1908 1709 11.863 B4259/6 Hinkley R4 S21 4 2 0.25 19+25+31 outer 11 Winfrith 08/08/1979 12/08/79 16:19:12 02/11/1984 2.012 22775 22782 187 1908 1709 13.331 B3284/1 Hinkley R3 P25 4 2 0.25 1+3+5 inner 12 Harwell 26/04/1979 01/06/1985 2.012 26276 22217 183 2228 1966 11.301 B3284/2 Hinkley R3 P25 4 2 0.25 7+11+15 middle 12 Harwell 26/04/1979 01/06/1985 2.012 26276 23258 183 2228 1966 11.830 B3284/3 Hinkley R3 P25 4 2 0.25 19+25+31 outer 12 Harwell 26/04/1979 01/06/1985 2.012 26276 26012 183 2228 1966 13.231 B3284/4 Hinkley R3 P25 4 2 0.25 1+3+5 inner 12 Winfrith 26/04/1979 01/06/1985 2.012 26276 22049 183 2228 1966 11.215 B3284/5 Hinkley R3 P25 4 2 0.25 7+11+15 middle 12 Winfrith 26/04/1979 01/06/1985 2.012 26276 23593 183 2228 1966 12.000 IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 37 of 115 RAT 1972 Issue 02 RAWG/P(01)04
PIE Ref. No / Reactor Channel Element Element Pellet Pin Ring Pellet Laboratory Load Date First Power Date6 Shutdown Discharge Enrichment Element Sample PIST8 Elapsed On-Power Mean Sample Position Design Bore Date Date (U235 % g/g) Irradiation Irradiation7 Time9 Time10 On-Power number (d) 11 (Stage) (inch) (MWd/t) (MWd/t) (d) (d) Rating (MW/t) B3284/6 Hinkley R3 P25 4 2 0.25 19+25+31 outer 12 Winfrith 26/04/1979 01/06/1985 2.012 26276 26012 183 2228 1966 13.231 B3362/1 Hinkley R3 W25 4 2 0.25 1+3+5 inner 12 Harwell 12/11/1981 03/04/1986 01/07/1986 2.55 20745 18613 183 1603 1461 12.740 B3362/2 Hinkley R3 W25 4 2 0.25 7+11+15 middle 12 Harwell 12/11/1981 03/04/1986 01/07/1986 2.55 20745 19868 183 1603 1461 13.599 B3362/3 Hinkley R3 W25 4 2 0.25 19+25+31 outer 12 Harwell 12/11/1981 03/04/1986 01/07/1986 2.55 20745 22405 183 1603 1461 15.335 B3362/4 Hinkley R3 W25 4 2 0.25 1+3+5 inner 12 Winfrith 12/11/1981 03/04/1986 01/07/1986 2.55 20745 18731 183 1603 1461 12.821 B3362/5 Hinkley R3 W25 4 2 0.25 7+11+15 middle 12 Winfrith 12/11/1981 03/04/1986 01/07/1986 2.55 20745 19607 183 1603 1461 13.420 B3362/6 Hinkley R3 W25 4 2 0.25 19+25+31 outer 12 Winfrith 12/11/1981 03/04/1986 01/07/1986 2.55 20745 22622 183 1603 1461 15.484
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 38 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 7: Cooling times (days) for the AGR sample measurements.12
PIE Ref. No / U, Pu, Nd Am241 Cm242, Fission PIE Ref. No / U, Pu, Nd Am241 Cm242, Fission PIE Ref. No / U, Pu, Nd Am241 Cm242, Fission Sample number and Cm244 Products Sample number and Cm244 Products Sample number and Cm244 Products
B4001/1 522 — — — C3139/1 266 274 274 — B3221/1 358 403 403 1380 B4001/2 553 — — — C3139/2 266 275 275 — B3221/2 358 403 403 1313 B4001/3 553 — — — C3139/3 266 279 279 — B3221/3 358 404 404 1313 B4001/4 553 — — — C3139/4 376 274 274 — B3221/4 520 520 520 — B4001/5 553 — — — C3139/5 376 275 275 — B3221/5 520 520 520 — B4001/6 553 — — — C3139/6 376 279 279 — B3221/6 520 520 520 — B4040/1 243 — — — B4175/1 390 418 418 — B4259/1 480 634 536 1035 B4040/2 243 — — — B4175/2 395 422 422 — B4259/2 480 637 536 1036 B4040/3 243 — — — B4175/3 401 423 423 — B4259/3 480 639 536 1036 B4040/4 182 — — — B4175/4 499 554 554 — B4259/4 500 500 500 — B4040/5 182 — — — B4175/5 499 555 555 — B4259/5 500 500 500 — B4040/6 182 — — — B4175/6 499 556 556 — B4259/6 500 500 500 — B4040/7 243 — — — B4180/1 353 — — — B3284/1 530 599 599 825 B4040/8 243 — — — B4180/2 353 — — — B3284/2 530 599 599 828 B4040/9 243 — — — B4180/3 353 — — — B3284/3 530 599 599 828 B3065/1 221 — — — B4180/4 353 — — — B3284/4 599 599 599 — B3065/2 271 — — — B4180/5 353 — — — B3284/5 599 599 599 — B3065/3 271 — — — B4180/6 353 — — — B3284/6 599 599 599 — B3086/1 452 390 390 — B4180/7 353 — — — B3362/1 662 733 733 697 B3086/2 452 394 394 — B4180/8 353 — — — B3362/2 662 735 735 698 B3086/3 452 403 403 — B4181/1 353 — — — B3362/3 662 739 739 699 B3086/4 402 390 390 — B4181/2 353 — — — B3362/4 690 690 690 — B3086/5 410 394 394 — B4181/3 353 — — — B3362/5 690 690 690 — B3086/6 413 403 403 — B4181/4 353 — — — B3362/6 690 690 690 —
12 The cooling times have been condensed into a maximum of four. Resulting differences compared to the true cooling times have a negligible effect on the results. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 39 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 8: AGR results for the uranium isotopes.
U234/U (% a/a) U235/U (% a/a) U236/U (% a/a) U238/U (% a/a) C E C/E C E C/E C E C/E C E C/E B4001/1 0.01937 0.02 +/- 0.01 0.97 +/- 0.48 1.914 1.92 +/- 0.01 1.00 +/- 0.01 0.05015 0.06 +/- 0.01 0.84 +/- 0.14 98.02 98.00 +/- 0.10 1.00 +/- 0.00 B4001/2 0.01934 0.02 +/- 0.01 0.97 +/- 0.48 1.898 1.90 +/- 0.01 1.00 +/- 0.01 0.05271 0.05 +/- 0.01 1.05 +/- 0.21 98.03 98.03 +/- 0.10 1.00 +/- 0.00 B4001/3 0.01930 0.02 +/- 0.01 0.97 +/- 0.48 1.878 1.88 +/- 0.01 1.00 +/- 0.01 0.05583 0.06 +/- 0.01 0.93 +/- 0.16 98.05 98.04 +/- 0.10 1.00 +/- 0.00 B4001/4 0.01929 0.02 +/- 0.01 0.96 +/- 0.48 1.883 1.88 +/- 0.01 1.00 +/- 0.01 0.05541 0.05 +/- 0.01 1.11 +/- 0.22 98.04 98.05 +/- 0.10 1.00 +/- 0.00 B4001/5 0.01926 0.02 +/- 0.01 0.96 +/- 0.48 1.870 1.87 +/- 0.01 1.00 +/- 0.01 0.05745 0.05 +/- 0.01 1.15 +/- 0.23 98.05 98.06 +/- 0.10 1.00 +/- 0.00 B4001/6 0.01924 0.02 +/- 0.01 0.96 +/- 0.48 1.857 1.85 +/- 0.01 1.00 +/- 0.01 0.05945 0.06 +/- 0.01 0.99 +/- 0.17 98.07 98.07 +/- 0.10 1.00 +/- 0.00 B4040/1 0.01264 0.016 +/- 0.001 0.79 +/- 0.05 1.009 1.023 +/- 0.001 0.99 +/- 0.00 0.1204 0.135 +/- 0.001 0.89 +/- 0.01 98.86 98.826 +/- 0.010 1.00 +/- 0.00 B4040/2 0.01264 0.016 +/- 0.001 0.79 +/- 0.05 0.9998 0.986 +/- 0.001 1.01 +/- 0.00 0.1216 0.141 +/- 0.001 0.86 +/- 0.01 98.87 98.857 +/- 0.010 1.00 +/- 0.00 B4040/3 0.01247 0.016 +/- 0.001 0.78 +/- 0.05 0.9331 0.923 +/- 0.001 1.01 +/- 0.00 0.1314 0.151 +/- 0.001 0.87 +/- 0.01 98.92 98.910 +/- 0.010 1.00 +/- 0.00 B4040/4 0.01268 0.015 +/- 0.001 0.85 +/- 0.06 1.021 1.021 +/- 0.002 1.00 +/- 0.00 0.1184 0.135 +/- 0.001 0.88 +/- 0.01 98.85 98.829 +/- 0.002 1.00 +/- 0.00 B4040/5 0.01262 0.014 +/- 0.001 0.90 +/- 0.06 0.9926 0.985 +/- 0.002 1.01 +/- 0.00 0.1228 0.139 +/- 0.001 0.88 +/- 0.01 98.87 98.861 +/- 0.002 1.00 +/- 0.00 B4040/6 0.01243 0.015 +/- 0.001 0.83 +/- 0.06 0.9206 0.922 +/- 0.002 1.00 +/- 0.00 0.1334 0.150 +/- 0.001 0.89 +/- 0.01 98.93 98.913 +/- 0.002 1.00 +/- 0.00 B4040/7 0.01242 0.016 +/- 0.001 0.78 +/- 0.05 0.9437 0.921 +/- 0.001 1.02 +/- 0.00 0.1310 0.152 +/- 0.001 0.86 +/- 0.01 98.91 98.911 +/- 0.010 1.00 +/- 0.00 B4040/8 0.01237 0.016 +/- 0.001 0.77 +/- 0.05 0.9189 0.888 +/- 0.001 1.03 +/- 0.00 0.1347 0.155 +/- 0.001 0.87 +/- 0.01 98.93 98.941 +/- 0.010 1.00 +/- 0.00 B4040/9 0.01228 0.016 +/- 0.001 0.77 +/- 0.05 0.8770 0.845 +/- 0.001 1.04 +/- 0.00 0.1403 0.163 +/- 0.001 0.86 +/- 0.01 98.97 98.976 +/- 0.010 1.00 +/- 0.00 B3065/1 0.01742 0.016 +/- 0.001 1.09 +/- 0.07 1.306 1.276 +/- 0.001 1.02 +/- 0.00 0.1522 0.165 +/- 0.001 0.92 +/- 0.01 98.52 98.543 +/- 0.001 1.00 +/- 0.00 B3065/2 0.01727 0.018 +/- 0.001 0.96 +/- 0.05 1.249 1.218 +/- 0.001 1.03 +/- 0.00 0.1610 0.184 +/- 0.001 0.88 +/- 0.00 98.57 98.580 +/- 0.002 1.00 +/- 0.00 B3065/3 0.01700 0.018 +/- 0.001 0.94 +/- 0.05 1.154 1.116 +/- 0.001 1.03 +/- 0.00 0.1748 0.208 +/- 0.001 0.84 +/- 0.00 98.65 98.658 +/- 0.001 1.00 +/- 0.00 B3086/1 0.01670 0.04 +/- 0.01 0.42 +/- 0.10 1.122 1.13 +/- 0.01 0.99 +/- 0.01 0.1825 0.20 +/- 0.01 0.91 +/- 0.05 98.68 98.63 +/- 0.10 1.00 +/- 0.00 B3086/2 0.01657 0.04 +/- 0.01 0.41 +/- 0.10 1.071 1.06 +/- 0.01 1.01 +/- 0.01 0.1902 0.21 +/- 0.01 0.91 +/- 0.04 98.72 98.69 +/- 0.10 1.00 +/- 0.00 B3086/3 0.01627 0.03 +/- 0.01 0.54 +/- 0.18 0.9726 0.96 +/- 0.01 1.01 +/- 0.01 0.2037 0.24 +/- 0.01 0.85 +/- 0.04 98.81 98.77 +/- 0.10 1.00 +/- 0.00 B3086/4 0.01681 0.016 +/- 0.001 1.05 +/- 0.07 1.150 1.135 +/- 0.002 1.01 +/- 0.00 0.1780 0.193 +/- 0.001 0.92 +/- 0.00 98.66 98.656 +/- 0.003 1.00 +/- 0.00 B3086/5 0.01667 0.016 +/- 0.001 1.04 +/- 0.07 1.095 1.073 +/- 0.002 1.02 +/- 0.00 0.1863 0.203 +/- 0.001 0.92 +/- 0.00 98.70 98.708 +/- 0.003 1.00 +/- 0.00 B3086/6 0.01639 0.018 +/- 0.001 0.91 +/- 0.05 1.001 0.973 +/- 0.001 1.03 +/- 0.00 0.1992 0.227 +/- 0.001 0.88 +/- 0.00 98.78 98.782 +/- 0.002 1.00 +/- 0.00 C3139/1 0.01577 0.015 +/- 0.001 1.05 +/- 0.07 0.9083 0.874 +/- 0.001 1.04 +/- 0.00 0.2170 0.228 +/- 0.001 0.95 +/- 0.00 98.86 98.883 +/- 0.010 1.00 +/- 0.00 C3139/2 0.01559 0.015 +/- 0.001 1.04 +/- 0.07 0.8494 0.807 +/- 0.001 1.05 +/- 0.00 0.2256 0.237 +/- 0.001 0.95 +/- 0.00 98.91 98.941 +/- 0.010 1.00 +/- 0.00 C3139/3 0.01512 0.018 +/- 0.001 0.84 +/- 0.05 0.7286 0.690 +/- 0.001 1.06 +/- 0.00 0.2413 0.286 +/- 0.001 0.84 +/- 0.00 99.01 99.006 +/- 0.010 1.00 +/- 0.00 C3139/4 0.01577 0.015 +/- 0.001 1.05 +/- 0.07 0.9074 0.865 +/- 0.002 1.05 +/- 0.00 0.2171 0.224 +/- 0.001 0.97 +/- 0.00 98.86 98.896 +/- 0.003 1.00 +/- 0.00 C3139/5 0.01581 0.015 +/- 0.001 1.05 +/- 0.07 0.8945 0.785 +/- 0.002 1.14 +/- 0.00 0.2184 0.222 +/- 0.001 0.98 +/- 0.00 98.87 98.978 +/- 0.003 1.00 +/- 0.00 C3139/6 0.01513 0.018 +/- 0.001 0.84 +/- 0.05 0.7272 0.692 +/- 0.002 1.05 +/- 0.00 0.2415 0.285 +/- 0.001 0.85 +/- 0.00 99.02 99.005 +/- 0.003 1.00 +/- 0.00 B4175/1 0.01498 0.015 +/- 0.001 1.00 +/- 0.07 0.7484 0.710 +/- 0.001 1.05 +/- 0.00 0.2422 0.264 +/- 0.001 0.92 +/- 0.00 99.00 99.011 +/- 0.010 1.00 +/- 0.00 B4175/2 0.01475 0.015 +/- 0.001 0.98 +/- 0.07 0.6849 0.642 +/- 0.001 1.07 +/- 0.00 0.2512 0.273 +/- 0.001 0.92 +/- 0.00 99.05 99.070 +/- 0.010 1.00 +/- 0.00 B4175/3 0.01420 0.015 +/- 0.001 0.95 +/- 0.06 0.5643 0.527 +/- 0.001 1.07 +/- 0.00 0.2655 0.276 +/- 0.001 0.96 +/- 0.00 99.15 99.182 +/- 0.010 1.00 +/- 0.00 B4175/4 0.01510 0.015 +/- 0.001 1.01 +/- 0.07 0.7704 0.727 +/- 0.002 1.06 +/- 0.00 0.2388 0.268 +/- 0.001 0.89 +/- 0.00 98.98 98.989 +/- 0.003 1.00 +/- 0.00 B4175/5 0.01478 0.014 +/- 0.001 1.06 +/- 0.08 0.6875 0.616 +/- 0.002 1.12 +/- 0.00 0.2509 0.258 +/- 0.001 0.97 +/- 0.00 99.05 99.112 +/- 0.003 1.00 +/- 0.00 B4175/6 0.01418 0.015 +/- 0.001 0.95 +/- 0.06 0.5604 0.515 +/- 0.002 1.09 +/- 0.00 0.2661 0.267 +/- 0.001 1.00 +/- 0.00 99.16 99.203 +/- 0.003 1.00 +/- 0.00 B4180/1 0.01991 0.03 +/- 0.01 0.66 +/- 0.22 1.015 0.97 +/- 0.01 1.05 +/- 0.01 0.2796 0.37 +/- 0.01 0.76 +/- 0.02 98.69 98.63 +/- 0.10 1.00 +/- 0.00
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 40 of 115 RAT 1972 Issue 02 RAWG/P(01)04
U234/U (% a/a) U235/U (% a/a) U236/U (% a/a) U238/U (% a/a) C E C/E C E C/E C E C/E C E C/E B4180/2 0.02019 0.03 +/- 0.01 0.67 +/- 0.22 1.070 0.98 +/- 0.01 1.09 +/- 0.01 0.2710 0.34 +/- 0.01 0.80 +/- 0.02 98.64 98.65 +/- 0.10 1.00 +/- 0.00 B4180/3 0.02027 0.03 +/- 0.01 0.68 +/- 0.23 1.087 1.05 +/- 0.01 1.03 +/- 0.01 0.2683 0.36 +/- 0.01 0.75 +/- 0.02 98.63 98.56 +/- 0.10 1.00 +/- 0.00 B4180/4 0.02002 0.02 +/- 0.01 1.00 +/- 0.50 1.036 0.99 +/- 0.01 1.05 +/- 0.01 0.2762 0.31 +/- 0.01 0.89 +/- 0.03 98.67 98.68 +/- 0.10 1.00 +/- 0.00 B4180/5 0.02016 0.03 +/- 0.01 0.67 +/- 0.22 1.064 1.03 +/- 0.01 1.03 +/- 0.01 0.2719 0.36 +/- 0.01 0.76 +/- 0.02 98.64 98.58 +/- 0.10 1.00 +/- 0.00 B4180/6 0.02055 0.02 +/- 0.01 1.03 +/- 0.51 1.144 1.10 +/- 0.01 1.04 +/- 0.01 0.2593 0.29 +/- 0.01 0.89 +/- 0.03 98.58 98.59 +/- 0.10 1.00 +/- 0.00 B4180/7 0.02038 0.02 +/- 0.01 1.02 +/- 0.51 1.109 1.04 +/- 0.01 1.07 +/- 0.01 0.2648 0.29 +/- 0.01 0.91 +/- 0.03 98.60 98.65 +/- 0.10 1.00 +/- 0.00 B4180/8 0.02088 0.02 +/- 0.01 1.04 +/- 0.52 1.216 1.16 +/- 0.01 1.05 +/- 0.01 0.2479 0.28 +/- 0.01 0.89 +/- 0.03 98.51 98.54 +/- 0.10 1.00 +/- 0.00 B4181/1 0.02041 0.03 +/- 0.01 0.68 +/- 0.23 1.115 1.01 +/- 0.01 1.10 +/- 0.01 0.2639 0.37 +/- 0.01 0.71 +/- 0.02 98.60 98.59 +/- 0.10 1.00 +/- 0.00 B4181/2 0.02024 0.03 +/- 0.01 0.67 +/- 0.22 1.081 1.01 +/- 0.01 1.07 +/- 0.01 0.2693 0.37 +/- 0.01 0.73 +/- 0.02 98.63 98.59 +/- 0.10 1.00 +/- 0.00 B4181/3 0.02044 0.02 +/- 0.01 1.02 +/- 0.51 1.121 1.06 +/- 0.01 1.06 +/- 0.01 0.2630 0.29 +/- 0.01 0.91 +/- 0.03 98.59 98.63 +/- 0.10 1.00 +/- 0.00 B4181/4 0.02038 0.03 +/- 0.01 0.68 +/- 0.23 1.109 1.06 +/- 0.01 1.05 +/- 0.01 0.2648 0.29 +/- 0.01 0.91 +/- 0.03 98.61 98.03 +/- 0.10 1.01 +/- 0.00 B3221/1 0.01614 0.015 +/- 0.001 1.08 +/- 0.07 0.7586 0.708 +/- 0.001 1.07 +/- 0.00 0.2668 0.267 +/- 0.001 1.00 +/- 0.00 98.96 99.010 +/- 0.010 1.00 +/- 0.00 B3221/2 0.01585 0.015 +/- 0.001 1.06 +/- 0.07 0.6851 0.638 +/- 0.001 1.07 +/- 0.00 0.2773 0.278 +/- 0.001 1.00 +/- 0.00 99.02 99.069 +/- 0.010 1.00 +/- 0.00 B3221/3 0.01532 0.014 +/- 0.001 1.09 +/- 0.08 0.5746 0.529 +/- 0.001 1.09 +/- 0.00 0.2893 0.292 +/- 0.001 0.99 +/- 0.00 99.12 99.165 +/- 0.010 1.00 +/- 0.00 B3221/4 0.01623 0.015 +/- 0.001 1.08 +/- 0.07 0.7726 0.709 +/- 0.002 1.09 +/- 0.00 0.2646 0.267 +/- 0.001 0.99 +/- 0.00 98.95 99.008 +/- 0.003 1.00 +/- 0.00 B3221/5 0.01607 0.015 +/- 0.001 1.07 +/- 0.07 0.7207 0.633 +/- 0.002 1.14 +/- 0.00 0.2718 0.277 +/- 0.001 0.98 +/- 0.00 98.99 99.070 +/- 0.003 1.00 +/- 0.00 B3221/6 0.01549 0.014 +/- 0.001 1.11 +/- 0.08 0.5983 0.530 +/- 0.002 1.13 +/- 0.00 0.2859 0.291 +/- 0.001 0.98 +/- 0.00 99.10 99.165 +/- 0.003 1.00 +/- 0.00 B4259/1 0.01420 0.013 +/- 0.001 1.09 +/- 0.08 0.5942 0.541 +/- 0.001 1.10 +/- 0.00 0.2649 0.263 +/- 0.002 1.01 +/- 0.01 99.13 99.183 +/- 0.010 1.00 +/- 0.00 B4259/2 0.01396 0.013 +/- 0.001 1.07 +/- 0.08 0.5377 0.484 +/- 0.001 1.11 +/- 0.00 0.2727 0.270 +/- 0.002 1.01 +/- 0.01 99.18 99.233 +/- 0.010 1.00 +/- 0.00 B4259/3 0.01340 0.012 +/- 0.001 1.12 +/- 0.09 0.4345 0.391 +/- 0.001 1.11 +/- 0.00 0.2830 0.279 +/- 0.002 1.01 +/- 0.01 99.27 99.318 +/- 0.010 1.00 +/- 0.00 B4259/4 0.01417 0.013 +/- 0.001 1.09 +/- 0.08 0.5902 0.541 +/- 0.002 1.09 +/- 0.00 0.2655 0.259 +/- 0.001 1.03 +/- 0.00 99.13 99.187 +/- 0.003 1.00 +/- 0.00 B4259/5 0.01391 0.013 +/- 0.001 1.07 +/- 0.08 0.5301 0.482 +/- 0.002 1.10 +/- 0.00 0.2738 0.268 +/- 0.002 1.02 +/- 0.01 99.18 99.240 +/- 0.003 1.00 +/- 0.00 B4259/6 0.01330 0.012 +/- 0.001 1.11 +/- 0.09 0.4216 0.390 +/- 0.002 1.08 +/- 0.01 0.2847 0.277 +/- 0.001 1.03 +/- 0.00 99.28 99.321 +/- 0.003 1.00 +/- 0.00 B3284/1 0.01331 0.012 +/- 0.001 1.11 +/- 0.09 0.4568 0.400 +/- 0.001 1.14 +/- 0.00 0.2852 0.277 +/- 0.001 1.03 +/- 0.00 99.25 99.311 +/- 0.001 1.00 +/- 0.00 B3284/2 0.01308 0.012 +/- 0.001 1.09 +/- 0.09 0.4087 0.347 +/- 0.001 1.18 +/- 0.00 0.2914 0.294 +/- 0.001 0.99 +/- 0.00 99.29 99.347 +/- 0.001 1.00 +/- 0.00 B3284/3 0.01242 0.012 +/- 0.001 1.03 +/- 0.09 0.3122 0.271 +/- 0.001 1.15 +/- 0.00 0.2988 0.296 +/- 0.001 1.01 +/- 0.00 99.38 99.421 +/- 0.001 1.00 +/- 0.00 B3284/4 0.01337 0.012 +/- 0.001 1.11 +/- 0.09 0.4635 0.398 +/- 0.002 1.16 +/- 0.01 0.2842 0.274 +/- 0.001 1.04 +/- 0.00 99.24 99.315 +/- 0.003 1.00 +/- 0.00 B3284/5 0.01299 0.012 +/- 0.001 1.08 +/- 0.09 0.3965 0.344 +/- 0.002 1.15 +/- 0.01 0.2932 0.291 +/- 0.001 1.01 +/- 0.00 99.30 99.354 +/- 0.003 1.00 +/- 0.00 B3284/6 0.01243 0.011 +/- 0.001 1.13 +/- 0.10 0.3122 0.268 +/- 0.002 1.16 +/- 0.01 0.2988 0.293 +/- 0.001 1.02 +/- 0.00 99.38 99.428 +/- 0.003 1.00 +/- 0.00 B3362/1 0.01993 0.019 +/- 0.002 1.05 +/- 0.11 1.001 0.955 +/- 0.005 1.05 +/- 0.01 0.2947 0.382 +/- 0.002 0.77 +/- 0.00 98.68 98.644 +/- 0.099 1.00 +/- 0.00 B3362/2 0.01962 0.018 +/- 0.002 1.09 +/- 0.12 0.9121 0.864 +/- 0.004 1.06 +/- 0.00 0.3075 0.371 +/- 0.002 0.83 +/- 0.00 98.76 98.747 +/- 0.099 1.00 +/- 0.00 B3362/3 0.01892 0.022 +/- 0.002 0.86 +/- 0.08 0.7565 0.720 +/- 0.004 1.05 +/- 0.01 0.3261 0.405 +/- 0.002 0.81 +/- 0.00 98.90 98.848 +/- 0.099 1.00 +/- 0.00 B3362/4 0.01989 0.019 +/- 0.001 1.05 +/- 0.06 0.9938 0.954 +/- 0.002 1.04 +/- 0.00 0.2959 0.382 +/- 0.001 0.77 +/- 0.00 98.69 98.645 +/- 0.001 1.00 +/- 0.00 B3362/5 0.01971 0.019 +/- 0.001 1.04 +/- 0.05 0.9280 0.867 +/- 0.001 1.07 +/- 0.00 0.3051 0.370 +/- 0.001 0.82 +/- 0.00 98.75 98.745 +/- 0.002 1.00 +/- 0.00 B3362/6 0.01885 0.022 +/- 0.001 0.86 +/- 0.04 0.7450 0.718 +/- 0.001 1.04 +/- 0.00 0.3278 0.401 +/- 0.001 0.82 +/- 0.00 98.91 98.858 +/- 0.002 1.00 +/- 0.00 Mean ; SD 0.94 ; 0.17 1.06 ; 0.05 0.92 ; 0.09 1.000 ; 0.001
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 41 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 9: AGR results for the plutonium isotopes (with respect to plutonium).
Pu238/Pu (% a/a) Pu239/Pu (% a/a) Pu240/Pu (% a/a) Pu241/Pu (% a/a) Pu242/Pu (% a/a) CE C/ECE C/ECEC/ECE C/ECEC/E B4001/1 95.50 95.80 +/- 0.10 1.00 +/- 0.00 4.225 3.97 +/- 0.01 1.06 +/- 0.00 0.2614 0.21 +/- 0.01 1.24 +/- 0.06 B4001/2 95.01 95.53 +/- 0.10 0.99 +/- 0.00 4.663 4.23 +/- 0.01 1.10 +/- 0.00 0.3062 0.23 +/- 0.01 1.33 +/- 0.06 B4001/3 94.43 95.01 +/- 0.10 0.99 +/- 0.00 5.190 4.71 +/- 0.01 1.10 +/- 0.00 0.3569 0.27 +/- 0.01 1.32 +/- 0.05 B4001/4 94.39 94.91 +/- 0.10 0.99 +/- 0.00 5.192 4.80 +/- 0.01 1.08 +/- 0.00 0.3977 0.27 +/- 0.01 1.47 +/- 0.05 B4001/5 94.02 94.68 +/- 0.10 0.99 +/- 0.00 5.520 5.01 +/- 0.01 1.10 +/- 0.00 0.4318 0.29 +/- 0.01 1.49 +/- 0.05 B4001/6 93.68 94.28 +/- 0.10 0.99 +/- 0.00 5.839 5.38 +/- 0.01 1.09 +/- 0.00 0.4541 0.32 +/- 0.01 1.42 +/- 0.04 B4040/1 0.1446 0.173 +/- 0.002 0.84 +/- 0.01 75.34 76.335 +/- 0.008 0.99 +/- 0.00 19.71 19.150 +/- 0.020 1.03 +/- 0.00 4.278 3.847 +/- 0.007 1.11 +/- 0.00 0.5283 0.495 +/- 0.001 1.07 +/- 0.00 B4040/2 0.1395 0.173 +/- 0.002 0.81 +/- 0.01 75.05 74.867 +/- 0.007 1.00 +/- 0.00 20.09 20.150 +/- 0.020 1.00 +/- 0.00 4.192 4.232 +/- 0.007 0.99 +/- 0.00 0.5272 0.578 +/- 0.002 0.91 +/- 0.00 B4040/3 0.1602 0.192 +/- 0.002 0.83 +/- 0.01 72.23 72.239 +/- 0.007 1.00 +/- 0.00 21.86 21.722 +/- 0.020 1.01 +/- 0.00 5.023 5.055 +/- 0.007 0.99 +/- 0.00 0.7319 0.792 +/- 0.002 0.92 +/- 0.00 B4040/4 0.1376 0.17 +/- 0.01 0.81 +/- 0.05 75.82 76.23 +/- 0.01 0.99 +/- 0.00 19.34 19.22 +/- 0.01 1.01 +/- 0.00 4.199 3.89 +/- 0.01 1.08 +/- 0.00 0.4978 0.49 +/- 0.01 1.02 +/- 0.02 B4040/5 0.1417 0.18 +/- 0.01 0.79 +/- 0.04 74.73 74.75 +/- 0.01 1.00 +/- 0.00 20.30 20.25 +/- 0.01 1.00 +/- 0.00 4.291 4.24 +/- 0.01 1.01 +/- 0.00 0.5454 0.58 +/- 0.01 0.94 +/- 0.02 B4040/6 0.1654 0.19 +/- 0.01 0.87 +/- 0.05 71.66 72.16 +/- 0.01 0.99 +/- 0.00 22.20 21.82 +/- 0.01 1.02 +/- 0.00 5.193 5.04 +/- 0.01 1.03 +/- 0.00 0.7738 0.79 +/- 0.01 0.98 +/- 0.01 B4040/7 0.1795 0.264 +/- 0.002 0.68 +/- 0.01 72.58 71.757 +/- 0.007 1.01 +/- 0.00 21.63 22.111 +/- 0.022 0.98 +/- 0.00 4.889 5.061 +/- 0.007 0.97 +/- 0.00 0.7138 0.807 +/- 0.002 0.88 +/- 0.00 B4040/8 0.1812 0.199 +/- 0.002 0.91 +/- 0.01 71.63 70.570 +/- 0.007 1.02 +/- 0.00 22.49 22.912 +/- 0.020 0.98 +/- 0.00 4.939 5.406 +/- 0.007 0.91 +/- 0.00 0.7594 0.913 +/- 0.002 0.83 +/- 0.00 B4040/9 0.1921 0.224 +/- 0.002 0.86 +/- 0.01 69.86 68.854 +/- 0.007 1.01 +/- 0.00 23.42 23.945 +/- 0.020 0.98 +/- 0.00 5.599 5.882 +/- 0.007 0.95 +/- 0.00 0.9330 1.095 +/- 0.002 0.85 +/- 0.00 B3065/1 0.1836 0.29 +/- 0.01 0.63 +/- 0.02 74.57 74.28 +/- 0.05 1.00 +/- 0.00 19.89 20.20 +/- 0.05 0.98 +/- 0.00 4.755 4.59 +/- 0.01 1.04 +/- 0.00 0.6015 0.64 +/- 0.01 0.94 +/- 0.01 B3065/2 0.1970 0.26 +/- 0.01 0.76 +/- 0.03 72.85 72.64 +/- 0.01 1.00 +/- 0.00 21.35 21.31 +/- 0.01 1.00 +/- 0.00 4.908 5.01 +/- 0.01 0.98 +/- 0.00 0.6933 0.77 +/- 0.01 0.90 +/- 0.01 B3065/3 0.2312 0.30 +/- 0.01 0.77 +/- 0.03 69.74 69.50 +/- 0.04 1.00 +/- 0.00 23.16 23.04 +/- 0.04 1.01 +/- 0.00 5.897 6.06 +/- 0.01 0.97 +/- 0.00 0.9738 1.10 +/- 0.01 0.89 +/- 0.01 B3086/1 0.3025 0.33 +/- 0.01 0.92 +/- 0.03 68.71 69.44 +/- 0.10 0.99 +/- 0.00 24.00 23.85 +/- 0.03 1.01 +/- 0.00 5.905 5.38 +/- 0.01 1.10 +/- 0.00 1.081 1.00 +/- 0.01 1.08 +/- 0.01 B3086/2 0.3137 0.35 +/- 0.01 0.90 +/- 0.03 67.08 67.60 +/- 0.10 0.99 +/- 0.00 25.37 24.96 +/- 0.02 1.02 +/- 0.00 6.036 5.89 +/- 0.02 1.02 +/- 0.00 1.195 1.20 +/- 0.01 1.00 +/- 0.01 B3086/3 0.3726 0.46 +/- 0.01 0.81 +/- 0.02 63.92 64.32 +/- 0.10 0.99 +/- 0.00 26.88 26.49 +/- 0.02 1.01 +/- 0.00 7.173 7.03 +/- 0.01 1.02 +/- 0.00 1.647 1.70 +/- 0.01 0.97 +/- 0.01 B3086/4 0.2833 0.32 +/- 0.01 0.89 +/- 0.03 69.57 69.54 +/- 0.03 1.00 +/- 0.00 23.39 23.75 +/- 0.02 0.98 +/- 0.00 5.757 5.40 +/- 0.01 1.07 +/- 0.00 0.9975 0.99 +/- 0.01 1.01 +/- 0.01 B3086/5 0.2968 0.35 +/- 0.01 0.85 +/- 0.02 67.84 67.73 +/- 0.01 1.00 +/- 0.00 24.84 24.83 +/- 0.01 1.00 +/- 0.00 5.903 5.89 +/- 0.01 1.00 +/- 0.00 1.116 1.20 +/- 0.01 0.93 +/- 0.01 B3086/6 0.3489 0.41 +/- 0.01 0.85 +/- 0.02 64.82 64.89 +/- 0.03 1.00 +/- 0.00 26.32 26.14 +/- 0.03 1.01 +/- 0.00 6.990 6.91 +/- 0.01 1.01 +/- 0.00 1.523 1.65 +/- 0.01 0.92 +/- 0.01 C3139/1 0.5505 0.61 +/- 0.02 0.90 +/- 0.03 61.76 61.31 +/- 0.10 1.01 +/- 0.00 28.52 29.42 +/- 0.05 0.97 +/- 0.00 7.302 6.79 +/- 0.02 1.08 +/- 0.00 1.869 1.87 +/- 0.02 1.00 +/- 0.01 C3139/2 0.5744 0.66 +/- 0.02 0.87 +/- 0.03 59.82 59.38 +/- 0.10 1.01 +/- 0.00 30.02 30.51 +/- 0.05 0.98 +/- 0.00 7.496 7.29 +/- 0.03 1.03 +/- 0.00 2.084 2.16 +/- 0.02 0.96 +/- 0.01 C3139/3 0.7244 0.84 +/- 0.02 0.86 +/- 0.02 56.05 55.83 +/- 0.05 1.00 +/- 0.00 31.42 31.45 +/- 0.03 1.00 +/- 0.00 8.837 8.73 +/- 0.02 1.01 +/- 0.00 2.971 3.15 +/- 0.01 0.94 +/- 0.00 C3139/4 0.5611 0.56 +/- 0.02 1.00 +/- 0.04 61.79 61.62 +/- 0.03 1.00 +/- 0.00 28.56 29.37 +/- 0.02 0.97 +/- 0.00 7.209 6.66 +/- 0.02 1.08 +/- 0.00 1.875 1.79 +/- 0.02 1.05 +/- 0.01 C3139/5 0.5360 0.59 +/- 0.02 0.91 +/- 0.03 61.34 60.74 +/- 0.03 1.01 +/- 0.00 29.13 29.41 +/- 0.02 0.99 +/- 0.00 7.121 7.15 +/- 0.02 1.00 +/- 0.00 1.871 2.11 +/- 0.02 0.89 +/- 0.01 C3139/6 0.7403 0.86 +/- 0.02 0.86 +/- 0.02 56.07 56.08 +/- 0.03 1.00 +/- 0.00 31.48 31.34 +/- 0.02 1.00 +/- 0.00 8.728 8.54 +/- 0.02 1.02 +/- 0.00 2.984 3.18 +/- 0.02 0.94 +/- 0.01 B4175/1 0.7208 0.93 +/- 0.02 0.78 +/- 0.02 56.66 55.12 +/- 0.05 1.03 +/- 0.00 31.79 33.11 +/- 0.03 0.96 +/- 0.00 8.107 7.91 +/- 0.02 1.02 +/- 0.00 2.715 2.93 +/- 0.01 0.93 +/- 0.00 B4175/2 0.7533 1.04 +/- 0.02 0.72 +/- 0.01 54.53 53.09 +/- 0.05 1.03 +/- 0.00 33.32 33.87 +/- 0.03 0.98 +/- 0.00 8.343 8.49 +/- 0.02 0.98 +/- 0.00 3.054 3.51 +/- 0.01 0.87 +/- 0.00 B4175/3 0.9526 1.20 +/- 0.02 0.79 +/- 0.01 50.88 49.90 +/- 0.05 1.02 +/- 0.00 34.20 34.19 +/- 0.03 1.00 +/- 0.00 9.657 9.79 +/- 0.02 0.99 +/- 0.00 4.316 4.92 +/- 0.01 0.88 +/- 0.00 B4175/4 0.6986 0.87 +/- 0.01 0.80 +/- 0.01 57.43 55.57 +/- 0.01 1.03 +/- 0.00 31.40 32.97 +/- 0.01 0.95 +/- 0.00 7.886 7.72 +/- 0.01 1.02 +/- 0.00 2.590 2.86 +/- 0.01 0.91 +/- 0.00 B4175/5 0.7558 0.96 +/- 0.01 0.79 +/- 0.01 54.68 53.56 +/- 0.01 1.02 +/- 0.00 33.31 33.77 +/- 0.01 0.99 +/- 0.00 8.225 8.29 +/- 0.01 0.99 +/- 0.00 3.040 3.43 +/- 0.01 0.89 +/- 0.00 B4175/6 0.9666 1.09 +/- 0.01 0.89 +/- 0.01 50.82 50.43 +/- 0.01 1.01 +/- 0.00 34.30 34.13 +/- 0.01 1.00 +/- 0.00 9.563 9.55 +/- 0.01 1.00 +/- 0.00 4.358 4.81 +/- 0.01 0.91 +/- 0.00 B4180/1 0.6593 0.89 +/- 0.02 0.74 +/- 0.02 58.50 56.96 +/- 0.10 1.03 +/- 0.00 29.68 31.23 +/- 0.06 0.95 +/- 0.00 8.597 8.13 +/- 0.04 1.06 +/- 0.01 2.569 2.79 +/- 0.02 0.92 +/- 0.01
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 42 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Pu238/Pu (% a/a) Pu239/Pu (% a/a) Pu240/Pu (% a/a) Pu241/Pu (% a/a) Pu242/Pu (% a/a) CE C/ECE C/ECEC/ECE C/ECEC/E B4180/2 0.6032 0.85 +/- 0.02 0.71 +/- 0.02 59.92 57.51 +/- 0.10 1.04 +/- 0.00 28.87 30.97 +/- 0.06 0.93 +/- 0.00 8.301 8.00 +/- 0.04 1.04 +/- 0.01 2.311 2.67 +/- 0.02 0.87 +/- 0.01 B4180/3 0.5866 0.70 +/- 0.02 0.84 +/- 0.02 60.35 59.30 +/- 0.10 1.02 +/- 0.00 28.62 29.92 +/- 0.06 0.96 +/- 0.00 8.209 7.73 +/- 0.04 1.06 +/- 0.01 2.235 2.35 +/- 0.02 0.95 +/- 0.01 B4180/4 0.6366 0.81 +/- 0.02 0.79 +/- 0.02 59.06 57.87 +/- 0.10 1.02 +/- 0.00 29.36 30.61 +/- 0.06 0.96 +/- 0.00 8.481 8.06 +/- 0.04 1.05 +/- 0.01 2.464 2.65 +/- 0.02 0.93 +/- 0.01 B4180/5 0.6086 0.75 +/- 0.02 0.81 +/- 0.02 59.77 58.65 +/- 0.10 1.02 +/- 0.00 28.95 30.21 +/- 0.06 0.96 +/- 0.00 8.330 7.91 +/- 0.04 1.05 +/- 0.01 2.336 2.48 +/- 0.02 0.94 +/- 0.01 B4180/6 0.5328 0.57 +/- 0.02 0.93 +/- 0.03 61.84 60.81 +/- 0.10 1.02 +/- 0.00 27.75 28.92 +/- 0.06 0.96 +/- 0.00 7.888 7.56 +/- 0.04 1.04 +/- 0.01 1.992 2.14 +/- 0.02 0.93 +/- 0.01 B4180/7 0.5648 0.68 +/- 0.02 0.83 +/- 0.02 60.95 59.70 +/- 0.10 1.02 +/- 0.00 28.28 30.47 +/- 0.06 0.93 +/- 0.00 8.081 7.02 +/- 0.04 1.15 +/- 0.01 2.136 2.13 +/- 0.02 1.00 +/- 0.01 B4180/8 0.4708 0.52 +/- 0.02 0.91 +/- 0.03 63.70 62.79 +/- 0.10 1.01 +/- 0.00 26.63 28.49 +/- 0.06 0.93 +/- 0.00 7.484 6.49 +/- 0.04 1.15 +/- 0.01 1.716 1.71 +/- 0.02 1.00 +/- 0.01 B4181/1 0.5614 0.71 +/- 0.02 0.79 +/- 0.02 61.09 58.74 +/- 0.10 1.04 +/- 0.00 28.19 30.92 +/- 0.06 0.91 +/- 0.00 8.046 7.27 +/- 0.04 1.11 +/- 0.01 2.112 2.36 +/- 0.02 0.89 +/- 0.01 B4181/2 0.5941 0.71 +/- 0.02 0.84 +/- 0.02 60.21 58.88 +/- 0.10 1.02 +/- 0.00 28.71 30.86 +/- 0.06 0.93 +/- 0.00 8.237 7.24 +/- 0.04 1.14 +/- 0.01 2.260 2.31 +/- 0.02 0.98 +/- 0.01 B4181/3 0.5559 0.65 +/- 0.02 0.86 +/- 0.03 61.24 59.95 +/- 0.10 1.02 +/- 0.00 28.10 30.08 +/- 0.06 0.93 +/- 0.00 8.015 7.14 +/- 0.04 1.12 +/- 0.01 2.088 2.18 +/- 0.02 0.96 +/- 0.01 B4181/4 0.5668 0.65 +/- 0.02 0.87 +/- 0.03 60.94 60.08 +/- 0.10 1.01 +/- 0.00 28.28 30.04 +/- 0.06 0.94 +/- 0.00 8.079 7.09 +/- 0.04 1.14 +/- 0.01 2.136 2.14 +/- 0.02 1.00 +/- 0.01 B3221/1 0.7397 0.84 +/- 0.02 0.88 +/- 0.02 54.91 52.36 +/- 0.05 1.05 +/- 0.00 32.76 34.94 +/- 0.03 0.94 +/- 0.00 8.526 8.41 +/- 0.02 1.01 +/- 0.00 3.067 3.45 +/- 0.01 0.89 +/- 0.00 B3221/2 0.7704 0.88 +/- 0.02 0.88 +/- 0.02 52.66 50.62 +/- 0.05 1.04 +/- 0.00 34.30 35.42 +/- 0.03 0.97 +/- 0.00 8.787 8.99 +/- 0.02 0.98 +/- 0.00 3.485 4.09 +/- 0.01 0.85 +/- 0.00 B3221/3 0.9518 1.01 +/- 0.02 0.94 +/- 0.02 49.72 47.94 +/- 0.05 1.04 +/- 0.00 34.62 35.42 +/- 0.03 0.98 +/- 0.00 9.992 10.13 +/- 0.02 0.99 +/- 0.00 4.711 5.50 +/- 0.01 0.86 +/- 0.00 B3221/4 0.7320 0.82 +/- 0.02 0.89 +/- 0.02 55.42 52.64 +/- 0.03 1.05 +/- 0.00 32.57 34.93 +/- 0.02 0.93 +/- 0.00 8.296 8.19 +/- 0.02 1.01 +/- 0.00 2.988 3.42 +/- 0.02 0.87 +/- 0.01 B3221/5 0.7371 0.90 +/- 0.02 0.82 +/- 0.02 53.81 50.82 +/- 0.03 1.06 +/- 0.00 33.75 35.41 +/- 0.02 0.95 +/- 0.00 8.452 8.79 +/- 0.02 0.96 +/- 0.00 3.250 4.08 +/- 0.02 0.80 +/- 0.00 B3221/6 0.9271 1.03 +/- 0.02 0.90 +/- 0.02 50.51 48.22 +/- 0.03 1.05 +/- 0.00 34.37 35.42 +/- 0.02 0.97 +/- 0.00 9.699 9.87 +/- 0.02 0.98 +/- 0.00 4.502 5.46 +/- 0.02 0.82 +/- 0.00 B4259/1 0.8869 0.97 +/- 0.03 0.91 +/- 0.03 51.62 49.21 +/- 0.05 1.05 +/- 0.00 34.89 36.89 +/- 0.04 0.95 +/- 0.00 8.803 8.67 +/- 0.03 1.02 +/- 0.00 3.794 4.26 +/- 0.03 0.89 +/- 0.01 B4259/2 0.9094 1.04 +/- 0.03 0.87 +/- 0.03 49.74 47.67 +/- 0.05 1.04 +/- 0.00 36.09 37.20 +/- 0.04 0.97 +/- 0.00 9.027 9.13 +/- 0.03 0.99 +/- 0.00 4.232 4.96 +/- 0.03 0.85 +/- 0.01 B4259/3 1.132 1.19 +/- 0.03 0.95 +/- 0.02 46.81 45.37 +/- 0.05 1.03 +/- 0.00 36.13 36.67 +/- 0.04 0.99 +/- 0.00 10.18 10.17 +/- 0.03 1.00 +/- 0.00 5.748 6.60 +/- 0.03 0.87 +/- 0.00 B4259/4 0.8938 0.97 +/- 0.02 0.92 +/- 0.02 51.51 49.25 +/- 0.03 1.05 +/- 0.00 34.97 36.88 +/- 0.02 0.95 +/- 0.00 8.800 8.62 +/- 0.02 1.02 +/- 0.00 3.827 4.27 +/- 0.02 0.90 +/- 0.00 B4259/5 0.9218 1.05 +/- 0.02 0.88 +/- 0.02 49.51 47.68 +/- 0.03 1.04 +/- 0.00 36.23 37.22 +/- 0.02 0.97 +/- 0.00 9.037 9.09 +/- 0.02 0.99 +/- 0.00 4.301 4.96 +/- 0.02 0.87 +/- 0.00 B4259/6 1.159 1.19 +/- 0.02 0.97 +/- 0.02 46.42 45.36 +/- 0.03 1.02 +/- 0.00 36.31 36.68 +/- 0.02 0.99 +/- 0.00 10.21 10.14 +/- 0.02 1.01 +/- 0.00 5.911 6.62 +/- 0.02 0.89 +/- 0.00 B3284/1 1.156 1.26 +/- 0.02 0.92 +/- 0.01 47.25 43.78 +/- 0.04 1.08 +/- 0.00 37.34 39.85 +/- 0.04 0.94 +/- 0.00 9.223 9.20 +/- 0.02 1.00 +/- 0.00 5.030 5.91 +/- 0.02 0.85 +/- 0.00 B3284/2 1.173 1.40 +/- 0.02 0.84 +/- 0.01 45.61 42.43 +/- 0.04 1.07 +/- 0.00 38.21 39.67 +/- 0.04 0.96 +/- 0.00 9.443 9.64 +/- 0.02 0.98 +/- 0.00 5.562 6.86 +/- 0.02 0.81 +/- 0.00 B3284/3 1.465 1.55 +/- 0.02 0.95 +/- 0.01 42.91 40.61 +/- 0.04 1.06 +/- 0.00 37.67 38.52 +/- 0.04 0.98 +/- 0.00 10.45 10.45 +/- 0.02 1.00 +/- 0.00 7.512 8.87 +/- 0.02 0.85 +/- 0.00 B3284/4 1.147 1.28 +/- 0.02 0.90 +/- 0.01 47.50 43.82 +/- 0.02 1.08 +/- 0.00 37.26 39.89 +/- 0.02 0.93 +/- 0.00 9.123 9.09 +/- 0.02 1.00 +/- 0.00 4.966 5.92 +/- 0.02 0.84 +/- 0.00 B3284/5 1.200 1.40 +/- 0.02 0.86 +/- 0.01 45.25 42.49 +/- 0.02 1.06 +/- 0.00 38.42 39.70 +/- 0.02 0.97 +/- 0.00 9.411 9.52 +/- 0.02 0.99 +/- 0.00 5.715 6.88 +/- 0.02 0.83 +/- 0.00 B3284/6 1.469 1.56 +/- 0.02 0.94 +/- 0.01 42.95 40.69 +/- 0.02 1.06 +/- 0.00 37.70 38.56 +/- 0.02 0.98 +/- 0.00 10.36 10.32 +/- 0.02 1.00 +/- 0.00 7.519 8.87 +/- 0.02 0.85 +/- 0.00 B3362/1 0.7176 1.01 +/- 0.02 0.71 +/- 0.01 57.52 55.57 +/- 0.11 1.04 +/- 0.00 31.09 32.65 +/- 0.07 0.95 +/- 0.00 8.012 7.87 +/- 0.03 1.02 +/- 0.00 2.660 2.90 +/- 0.01 0.92 +/- 0.00 B3362/2 0.7460 1.02 +/- 0.02 0.73 +/- 0.01 55.19 53.61 +/- 0.11 1.03 +/- 0.00 32.82 33.46 +/- 0.07 0.98 +/- 0.00 8.226 8.44 +/- 0.03 0.97 +/- 0.00 3.018 3.47 +/- 0.02 0.87 +/- 0.01 B3362/3 0.9580 1.22 +/- 0.02 0.79 +/- 0.01 51.61 50.46 +/- 0.10 1.02 +/- 0.00 33.64 33.73 +/- 0.07 1.00 +/- 0.00 9.530 9.72 +/- 0.04 0.98 +/- 0.00 4.259 4.87 +/- 0.02 0.87 +/- 0.00 B3362/4 0.7254 1.04 +/- 0.01 0.70 +/- 0.01 57.35 55.64 +/- 0.01 1.03 +/- 0.00 31.22 32.61 +/- 0.01 0.96 +/- 0.00 8.015 7.81 +/- 0.01 1.03 +/- 0.00 2.695 2.90 +/- 0.01 0.93 +/- 0.00 B3362/5 0.7299 1.06 +/- 0.01 0.69 +/- 0.01 55.61 53.69 +/- 0.01 1.04 +/- 0.00 32.59 33.41 +/- 0.01 0.98 +/- 0.00 8.134 8.37 +/- 0.01 0.97 +/- 0.00 2.936 3.46 +/- 0.01 0.85 +/- 0.00 B3362/6 0.9744 1.26 +/- 0.01 0.77 +/- 0.01 51.34 50.51 +/- 0.02 1.02 +/- 0.00 33.80 33.76 +/- 0.03 1.00 +/- 0.00 9.541 9.58 +/- 0.01 1.00 +/- 0.00 4.344 4.89 +/- 0.01 0.89 +/- 0.00 Mean ; SD 0.84 ; 0.08 1.02 ; 0.02 0.98 ; 0.04 1.05 ; 0.11 0.91 ; 0.06
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 43 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 10: AGR results for the plutonium isotopes (with respect to uranium).13
Pu238/U (1E-6 g/g) Pu239/U (1E-6 g/g) Pu240/U (1E-6 g/g) Pu241/U (1E-6 g/g) Pu242/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E B4001/1 5.393E2 4.97E2 1.08 2.386E1 2.06E1 1.16 1.476E0 1.09E0 1.35 B4001/2 5.980E2 5.41E2 1.10 2.935E1 2.40E1 1.22 1.927E0 1.30E0 1.48 B4001/3 6.726E2 6.65E2 1.01 3.697E1 3.30E1 1.12 2.542E0 1.89E0 1.34 B4001/4 6.625E2 6.24E2 1.06 3.644E1 3.15E1 1.16 2.791E0 1.77E0 1.57 B4001/5 7.069E2 6.49E2 1.09 4.150E1 3.43E1 1.21 3.247E0 1.99E0 1.63 B4001/6 7.544E2 6.85E2 1.10 4.702E1 3.91E1 1.20 3.657E0 2.33E0 1.57 B4040/1 3.906E0 4.66E0 0.84 2.036E3 2.06E3 0.99 5.324E2 5.16E2 1.03 1.156E2 1.04E2 1.12 1.427E1 1.33E1 1.07 B4040/2 3.815E0 4.67E0 0.82 2.053E3 2.02E3 1.01 5.495E2 5.44E2 1.01 1.147E2 1.14E2 1.00 1.442E1 1.56E1 0.92 B4040/3 4.841E0 5.86E0 0.83 2.182E3 2.21E3 0.99 6.605E2 6.63E2 1.00 1.518E2 1.54E2 0.98 2.211E1 2.42E1 0.91 B4040/4 3.645E0 4.42E0 0.83 2.008E3 1.98E3 1.01 5.123E2 4.99E2 1.03 1.112E2 1.01E2 1.10 1.319E1 1.27E1 1.04 B4040/5 3.923E0 4.89E0 0.80 2.068E3 2.03E3 1.02 5.618E2 5.50E2 1.02 1.188E2 1.15E2 1.03 1.509E1 1.57E1 0.96 B4040/6 5.089E0 5.76E0 0.88 2.206E3 2.19E3 1.01 6.833E2 6.62E2 1.03 1.598E2 1.53E2 1.05 2.382E1 2.40E1 0.99 B4040/7 5.374E0 8.00E0 0.67 2.174E3 2.17E3 1.00 6.478E2 6.70E2 0.97 1.464E2 1.53E2 0.95 2.138E1 2.45E1 0.87 B4040/8 5.602E0 6.16E0 0.91 2.215E3 2.19E3 1.01 6.952E2 7.09E2 0.98 1.527E2 1.67E2 0.91 2.348E1 2.83E1 0.83 B4040/9 6.273E0 7.36E0 0.85 2.281E3 2.26E3 1.01 7.648E2 7.87E2 0.97 1.828E2 1.93E2 0.95 3.047E1 3.60E1 0.85 B3065/1 5.439E0 8.93E0 0.61 2.209E3 2.29E3 0.97 5.890E2 6.22E2 0.95 1.408E2 1.41E2 1.00 1.781E1 1.97E1 0.90 B3065/2 6.181E0 8.38E0 0.74 2.285E3 2.34E3 0.98 6.698E2 6.87E2 0.98 1.540E2 1.61E2 0.95 2.175E1 2.48E1 0.88 B3065/3 7.945E0 1.08E1 0.74 2.396E3 2.49E3 0.96 7.957E2 8.26E2 0.96 2.026E2 2.17E2 0.93 3.346E1 3.95E1 0.85 B3086/1 1.094E1 1.14E1 0.96 2.486E3 2.40E3 1.04 8.681E2 8.23E2 1.05 2.136E2 1.86E2 1.15 3.912E1 3.45E1 1.13 B3086/2 1.180E1 1.25E1 0.94 2.523E3 2.42E3 1.04 9.542E2 8.93E2 1.07 2.270E2 2.11E2 1.08 4.495E1 4.29E1 1.05 B3086/3 1.510E1 1.86E1 0.81 2.591E3 2.60E3 1.00 1.090E3 1.07E3 1.02 2.908E2 2.84E2 1.02 6.675E1 6.86E1 0.97 B3086/4 9.972E0 1.11E1 0.90 2.449E3 2.41E3 1.02 8.233E2 8.23E2 1.00 2.027E2 1.87E2 1.08 3.511E1 3.43E1 1.02 B3086/5 1.092E1 1.26E1 0.87 2.496E3 2.44E3 1.02 9.138E2 8.95E2 1.02 2.172E2 2.12E2 1.02 4.107E1 4.32E1 0.95 B3086/6 1.381E1 1.61E1 0.86 2.565E3 2.56E3 1.00 1.041E3 1.03E3 1.01 2.766E2 2.72E2 1.02 6.028E1 6.50E1 0.93 C3139/1 2.403E1 2.65E1 0.91 2.696E3 2.66E3 1.01 1.245E3 1.28E3 0.97 3.188E2 2.95E2 1.08 8.158E1 8.12E1 1.00 C3139/2 2.598E1 2.94E1 0.88 2.706E3 2.64E3 1.02 1.358E3 1.36E3 1.00 3.391E2 3.25E2 1.04 9.427E1 9.62E1 0.98 C3139/3 3.545E1 4.11E1 0.86 2.743E3 2.73E3 1.00 1.537E3 1.54E3 1.00 4.324E2 4.28E2 1.01 1.454E2 1.54E2 0.94 C3139/4 2.449E1 2.39E1 1.02 2.697E3 2.63E3 1.03 1.247E3 1.25E3 0.99 3.147E2 2.84E2 1.11 8.182E1 7.64E1 1.07 C3139/5 2.338E1 2.51E1 0.93 2.676E3 2.58E3 1.04 1.271E3 1.25E3 1.02 3.106E2 3.04E2 1.02 8.162E1 8.96E1 0.91 C3139/6 3.622E1 4.14E1 0.88 2.743E3 2.70E3 1.02 1.540E3 1.51E3 1.02 4.271E2 4.11E2 1.04 1.460E2 1.53E2 0.95 B4175/1 3.539E1 4.50E1 0.79 2.782E3 2.67E3 1.04 1.561E3 1.60E3 0.97 3.981E2 3.83E2 1.04 1.333E2 1.42E2 0.94 B4175/2 3.829E1 5.20E1 0.74 2.772E3 2.65E3 1.04 1.693E3 1.69E3 1.00 4.240E2 4.24E2 1.00 1.552E2 1.75E2 0.89 B4175/3 5.203E1 6.52E1 0.80 2.779E3 2.71E3 1.03 1.868E3 1.86E3 1.01 5.275E2 5.32E2 0.99 2.357E2 2.67E2 0.88 B4175/4 3.371E1 3.98E1 0.85 2.772E3 2.54E3 1.09 1.515E3 1.51E3 1.00 3.806E2 3.53E2 1.08 1.250E2 1.31E2 0.96 B4175/5 3.830E1 4.55E1 0.84 2.770E3 2.54E3 1.09 1.688E3 1.60E3 1.05 4.167E2 3.93E2 1.06 1.540E2 1.63E2 0.95
13 Derived in this work from the isotopic ratios with respect to plutonium and the Pu/U ratio. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 44 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Pu238/U (1E-6 g/g) Pu239/U (1E-6 g/g) Pu240/U (1E-6 g/g) Pu241/U (1E-6 g/g) Pu242/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E B4175/6 5.288E1 5.60E1 0.94 2.780E3 2.59E3 1.07 1.876E3 1.75E3 1.07 5.231E2 4.91E2 1.07 2.384E2 2.47E2 0.96 B4180/1 3.172E1 4.06E1 0.78 2.815E3 2.60E3 1.08 1.428E3 1.42E3 1.00 4.137E2 3.71E2 1.12 1.236E2 1.27E2 0.97 B4180/2 2.808E1 3.82E1 0.74 2.790E3 2.58E3 1.08 1.344E3 1.39E3 0.97 3.865E2 3.59E2 1.08 1.076E2 1.20E2 0.90 B4180/3 2.703E1 3.03E1 0.89 2.781E3 2.56E3 1.08 1.319E3 1.29E3 1.02 3.782E2 3.34E2 1.13 1.030E2 1.02E2 1.01 B4180/4 3.023E1 3.72E1 0.81 2.805E3 2.66E3 1.06 1.394E3 1.41E3 0.99 4.028E2 3.70E2 1.09 1.170E2 1.22E2 0.96 B4180/5 2.843E1 3.37E1 0.84 2.792E3 2.63E3 1.06 1.353E3 1.36E3 1.00 3.892E2 3.55E2 1.10 1.091E2 1.11E2 0.98 B4180/6 2.368E1 2.46E1 0.96 2.749E3 2.62E3 1.05 1.233E3 1.25E3 0.99 3.507E2 3.26E2 1.08 8.854E1 9.23E1 0.96 B4180/7 2.566E1 2.88E1 0.89 2.769E3 2.53E3 1.10 1.285E3 1.29E3 1.00 3.671E2 2.97E2 1.24 9.705E1 9.02E1 1.08 B4180/8 1.998E1 2.07E1 0.97 2.703E3 2.50E3 1.08 1.130E3 1.13E3 1.00 3.176E2 2.58E2 1.23 7.281E1 6.80E1 1.07 B4181/1 2.542E1 2.93E1 0.87 2.766E3 2.43E3 1.14 1.276E3 1.28E3 1.00 3.643E2 3.01E2 1.21 9.561E1 9.76E1 0.98 B4181/2 2.747E1 3.03E1 0.91 2.784E3 2.52E3 1.11 1.327E3 1.32E3 1.01 3.809E2 3.09E2 1.23 1.045E2 9.87E1 1.06 B4181/3 2.508E1 2.76E1 0.91 2.763E3 2.54E3 1.09 1.268E3 1.28E3 0.99 3.616E2 3.03E2 1.19 9.418E1 9.25E1 1.02 B4181/4 2.576E1 2.80E1 0.92 2.769E3 2.59E3 1.07 1.285E3 1.30E3 0.99 3.671E2 3.06E2 1.20 9.708E1 9.23E1 1.05 B3221/1 3.693E1 4.17E1 0.89 2.742E3 2.60E3 1.05 1.635E3 1.74E3 0.94 4.257E2 4.18E2 1.02 1.531E2 1.71E2 0.89 B3221/2 3.994E1 4.53E1 0.88 2.730E3 2.60E3 1.05 1.778E3 1.82E3 0.98 4.555E2 4.62E2 0.98 1.807E2 2.10E2 0.86 B3221/3 5.261E1 5.62E1 0.94 2.748E3 2.67E3 1.03 1.914E3 1.97E3 0.97 5.523E2 5.63E2 0.98 2.604E2 3.06E2 0.85 B3221/4 3.614E1 4.08E1 0.89 2.737E3 2.62E3 1.04 1.608E3 1.74E3 0.92 4.097E2 4.08E2 1.00 1.476E2 1.70E2 0.87 B3221/5 3.728E1 4.54E1 0.82 2.721E3 2.56E3 1.06 1.707E3 1.79E3 0.96 4.275E2 4.43E2 0.96 1.644E2 2.06E2 0.80 B3221/6 5.038E1 5.74E1 0.88 2.745E3 2.69E3 1.02 1.867E3 1.98E3 0.95 5.270E2 5.50E2 0.96 2.446E2 3.05E2 0.80 B4259/1 4.690E1 5.06E1 0.93 2.730E3 2.57E3 1.06 1.845E3 1.92E3 0.96 4.655E2 4.52E2 1.03 2.006E2 2.22E2 0.90 B4259/2 4.959E1 5.57E1 0.89 2.712E3 2.55E3 1.06 1.968E3 1.99E3 0.99 4.923E2 4.89E2 1.01 2.308E2 2.65E2 0.87 B4259/3 6.598E1 6.89E1 0.96 2.727E3 2.63E3 1.04 2.105E3 2.12E3 0.99 5.932E2 5.89E2 1.01 3.350E2 3.82E2 0.88 B4259/4 4.739E1 5.07E1 0.93 2.731E3 2.57E3 1.06 1.854E3 1.93E3 0.96 4.665E2 4.51E2 1.04 2.029E2 2.23E2 0.91 B4259/5 5.052E1 5.65E1 0.89 2.713E3 2.57E3 1.06 1.985E3 2.00E3 0.99 4.953E2 4.89E2 1.01 2.357E2 2.67E2 0.88 B4259/6 6.814E1 6.91E1 0.99 2.729E3 2.63E3 1.04 2.134E3 2.13E3 1.00 5.999E2 5.89E2 1.02 3.474E2 3.85E2 0.90 B3284/1 6.725E1 7.07E1 0.95 2.748E3 2.46E3 1.12 2.172E3 2.24E3 0.97 5.364E2 5.16E2 1.04 2.926E2 3.31E2 0.88 B3284/2 6.997E1 8.05E1 0.87 2.720E3 2.44E3 1.12 2.279E3 2.28E3 1.00 5.631E2 5.54E2 1.02 3.317E2 3.94E2 0.84 B3284/3 9.315E1 9.46E1 0.98 2.728E3 2.48E3 1.10 2.395E3 2.35E3 1.02 6.644E2 6.38E2 1.04 4.777E2 5.41E2 0.88 B3284/4 6.636E1 7.19E1 0.92 2.747E3 2.46E3 1.12 2.155E3 2.24E3 0.96 5.276E2 5.11E2 1.03 2.872E2 3.33E2 0.86 B3284/5 7.212E1 8.10E1 0.89 2.720E3 2.46E3 1.11 2.310E3 2.30E3 1.01 5.657E2 5.51E2 1.03 3.436E2 3.98E2 0.86 B3284/6 9.333E1 9.66E1 0.97 2.728E3 2.52E3 1.08 2.395E3 2.39E3 1.00 6.584E2 6.39E2 1.03 4.777E2 5.49E2 0.87 B3362/1 3.516E1 5.06E1 0.69 2.818E3 2.79E3 1.01 1.523E3 1.64E3 0.93 3.925E2 3.95E2 0.99 1.303E2 1.45E2 0.90 B3362/2 3.784E1 5.26E1 0.72 2.799E3 2.76E3 1.01 1.665E3 1.72E3 0.97 4.173E2 4.35E2 0.96 1.531E2 1.79E2 0.86 B3362/3 5.226E1 6.90E1 0.76 2.815E3 2.85E3 0.99 1.835E3 1.91E3 0.96 5.199E2 5.49E2 0.95 2.323E2 2.75E2 0.84 B3362/4 3.567E1 5.26E1 0.68 2.820E3 2.81E3 1.00 1.535E3 1.65E3 0.93 3.941E2 3.95E2 1.00 1.325E2 1.47E2 0.90 B3362/5 3.670E1 5.54E1 0.66 2.796E3 2.81E3 1.00 1.639E3 1.75E3 0.94 4.089E2 4.37E2 0.93 1.476E2 1.81E2 0.82 B3362/6 5.346E1 7.17E1 0.75 2.817E3 2.87E3 0.98 1.854E3 1.92E3 0.97 5.235E2 5.45E2 0.96 2.383E2 2.78E2 0.86 Mean ; SD 0.86 ; 0.09 1.04 ; 0.04 1.01 ; 0.06 1.08 ; 0.15 0.93 ; 0.08
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 45 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 11: AGR results for the neodymium isotopes (with respect to neodymium).
Nd142/Nd (% a/a) Nd143/Nd (% a/a) Nd144/Nd (% a/a) Nd145/Nd (% a/a) Nd146/Nd (% a/a) Nd148/Nd (% a/a) Nd150/Nd (% a/a) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E B4001/1 0.01346 0.25 +/- 0.02 0.05 +/- 0.00 30.21 29.82 +/- 0.08 1.01 +/- 0.00 21.65 21.90 +/- 0.07 0.99 +/- 0.00 20.13 19.92 +/- 0.07 1.01 +/- 0.00 15.55 15.59 +/- 0.07 1.00 +/- 0.00 8.863 8.81 +/- 0.05 1.01 +/- 0.01 3.590 3.71 +/- 0.03 0.97 +/- 0.01 B4001/2 0.01497 0.19 +/- 0.02 0.08 +/- 0.01 30.03 29.63 +/- 0.08 1.01 +/- 0.00 22.07 22.11 +/- 0.06 1.00 +/- 0.00 20.03 19.99 +/- 0.06 1.00 +/- 0.00 15.47 15.64 +/- 0.06 0.99 +/- 0.00 8.822 8.78 +/- 0.05 1.00 +/- 0.01 3.569 3.66 +/- 0.03 0.98 +/- 0.01 B4001/3 0.01678 0.12 +/- 0.02 0.14 +/- 0.02 30.00 29.60 +/- 0.06 1.01 +/- 0.00 22.17 22.37 +/- 0.06 0.99 +/- 0.00 20.01 19.99 +/- 0.06 1.00 +/- 0.00 15.45 15.58 +/- 0.06 0.99 +/- 0.00 8.803 8.76 +/- 0.05 1.00 +/- 0.01 3.544 3.60 +/- 0.03 0.98 +/- 0.01 B4001/4 0.01693 0.05 +/- 0.05 0.34 +/- 0.34 29.94 29.50 +/- 0.09 1.02 +/- 0.00 22.10 22.43 +/- 0.04 0.99 +/- 0.00 20.01 20.02 +/- 0.06 1.00 +/- 0.00 15.50 15.59 +/- 0.06 0.99 +/- 0.00 8.848 8.82 +/- 0.05 1.00 +/- 0.01 3.592 3.59 +/- 0.03 1.00 +/- 0.01 B4001/5 0.01815 0.09 +/- 0.09 0.20 +/- 0.20 29.91 29.58 +/- 0.08 1.01 +/- 0.00 22.15 22.46 +/- 0.04 0.99 +/- 0.00 20.00 19.97 +/- 0.05 1.00 +/- 0.00 15.49 15.55 +/- 0.05 1.00 +/- 0.00 8.844 8.77 +/- 0.05 1.01 +/- 0.01 3.585 3.58 +/- 0.03 1.00 +/- 0.01 B4001/6 0.01920 0.06 +/- 0.06 0.32 +/- 0.32 29.92 29.52 +/- 0.08 1.01 +/- 0.00 22.23 22.55 +/- 0.04 0.99 +/- 0.00 19.99 19.98 +/- 0.06 1.00 +/- 0.00 15.47 15.55 +/- 0.05 0.99 +/- 0.00 8.821 8.77 +/- 0.05 1.01 +/- 0.01 3.557 3.57 +/- 0.03 1.00 +/- 0.01 B4040/1 0.1350 0.22 +/- 0.01 0.61 +/- 0.03 26.57 26.72 +/- 0.01 0.99 +/- 0.00 25.36 25.95 +/- 0.09 0.98 +/- 0.00 19.22 18.99 +/- 0.08 1.01 +/- 0.00 15.75 15.72 +/- 0.08 1.00 +/- 0.01 9.019 8.57 +/- 0.02 1.05 +/- 0.00 3.939 3.83 +/- 0.01 1.03 +/- 0.00 B4040/2 0.1364 0.24 +/- 0.01 0.57 +/- 0.02 26.52 26.29 +/- 0.01 1.01 +/- 0.00 25.44 25.87 +/- 0.09 0.98 +/- 0.00 19.21 19.05 +/- 0.08 1.01 +/- 0.00 15.74 15.76 +/- 0.08 1.00 +/- 0.01 9.011 8.89 +/- 0.02 1.01 +/- 0.00 3.931 3.90 +/- 0.01 1.01 +/- 0.00 B4040/3 0.1548 0.23 +/- 0.01 0.67 +/- 0.03 26.09 25.57 +/- 0.01 1.02 +/- 0.00 25.87 26.73 +/- 0.09 0.97 +/- 0.00 19.14 18.74 +/- 0.08 1.02 +/- 0.00 15.78 16.04 +/- 0.08 0.98 +/- 0.00 9.025 8.80 +/- 0.02 1.03 +/- 0.00 3.949 3.89 +/- 0.01 1.02 +/- 0.00 B4040/4 0.1321 0.21 +/- 0.01 0.63 +/- 0.03 26.83 26.20 +/- 0.02 1.02 +/- 0.00 24.82 25.75 +/- 0.02 0.96 +/- 0.00 19.36 19.09 +/- 0.02 1.01 +/- 0.00 15.84 15.82 +/- 0.02 1.00 +/- 0.00 9.069 8.96 +/- 0.02 1.01 +/- 0.00 3.956 3.97 +/- 0.01 1.00 +/- 0.00 B4040/5 0.1396 0.13 +/- 0.01 1.07 +/- 0.08 26.64 26.04 +/- 0.02 1.02 +/- 0.00 25.00 25.86 +/- 0.02 0.97 +/- 0.00 19.33 19.11 +/- 0.02 1.01 +/- 0.00 15.85 15.86 +/- 0.02 1.00 +/- 0.00 9.075 9.01 +/- 0.02 1.01 +/- 0.00 3.962 3.99 +/- 0.01 0.99 +/- 0.00 B4040/6 0.1601 0.17 +/- 0.01 0.94 +/- 0.06 26.16 25.55 +/- 0.02 1.02 +/- 0.00 25.46 26.33 +/- 0.02 0.97 +/- 0.00 19.24 19.01 +/- 0.02 1.01 +/- 0.00 15.90 15.89 +/- 0.02 1.00 +/- 0.00 9.093 9.03 +/- 0.02 1.01 +/- 0.00 3.984 4.02 +/- 0.01 0.99 +/- 0.00 B4040/7 0.1566 0.21 +/- 0.01 0.75 +/- 0.04 26.10 25.75 +/- 0.01 1.01 +/- 0.00 25.73 26.59 +/- 0.09 0.97 +/- 0.00 19.12 18.93 +/- 0.08 1.01 +/- 0.00 15.84 15.75 +/- 0.08 1.01 +/- 0.01 9.064 8.86 +/- 0.02 1.02 +/- 0.00 3.989 3.91 +/- 0.01 1.02 +/- 0.00 B4040/8 0.1632 0.24 +/- 0.01 0.68 +/- 0.03 25.93 25.67 +/- 0.01 1.01 +/- 0.00 25.90 26.54 +/- 0.09 0.98 +/- 0.00 19.10 18.94 +/- 0.08 1.01 +/- 0.00 15.85 15.75 +/- 0.08 1.01 +/- 0.01 9.067 8.92 +/- 0.02 1.02 +/- 0.00 3.992 3.94 +/- 0.01 1.01 +/- 0.00 B4040/9 0.1742 0.22 +/- 0.01 0.79 +/- 0.04 25.66 26.72 +/- 0.01 0.96 +/- 0.00 26.20 25.95 +/- 0.09 1.01 +/- 0.00 19.06 18.99 +/- 0.08 1.00 +/- 0.00 15.85 15.72 +/- 0.08 1.01 +/- 0.01 9.065 8.57 +/- 0.02 1.06 +/- 0.00 3.992 3.83 +/- 0.01 1.04 +/- 0.00 B3065/1 0.1470 0.17 +/- 0.01 0.86 +/- 0.05 26.81 26.17 +/- 0.01 1.02 +/- 0.00 24.65 25.48 +/- 0.03 0.97 +/- 0.00 19.42 19.18 +/- 0.01 1.01 +/- 0.00 15.98 16.00 +/- 0.01 1.00 +/- 0.00 9.071 9.00 +/- 0.01 1.01 +/- 0.00 3.921 4.01 +/- 0.01 0.98 +/- 0.00 B3065/2 0.1587 0.14 +/- 0.02 1.13 +/- 0.16 26.35 25.76 +/- 0.01 1.02 +/- 0.00 25.39 26.24 +/- 0.01 0.97 +/- 0.00 19.26 19.04 +/- 0.01 1.01 +/- 0.00 15.91 15.93 +/- 0.01 1.00 +/- 0.00 9.026 8.95 +/- 0.01 1.01 +/- 0.00 3.908 3.94 +/- 0.01 0.99 +/- 0.00 B3065/3 0.1805 0.11 +/- 0.03 1.64 +/- 0.45 25.84 25.21 +/- 0.01 1.02 +/- 0.00 25.89 26.84 +/- 0.01 0.96 +/- 0.00 19.17 18.94 +/- 0.01 1.01 +/- 0.00 15.96 15.98 +/- 0.01 1.00 +/- 0.00 9.036 8.96 +/- 0.01 1.01 +/- 0.00 3.921 3.96 +/- 0.01 0.99 +/- 0.00 B3086/1 0.1970 0.31 +/- 0.05 0.64 +/- 0.10 25.14 24.77 +/- 0.05 1.01 +/- 0.00 27.22 27.81 +/- 0.03 0.98 +/- 0.00 18.77 18.61 +/- 0.02 1.01 +/- 0.00 15.82 15.76 +/- 0.05 1.00 +/- 0.00 8.937 8.83 +/- 0.01 1.01 +/- 0.00 3.928 3.91 +/- 0.04 1.00 +/- 0.01 B3086/2 0.2098 0.31 +/- 0.05 0.68 +/- 0.11 24.84 24.27 +/- 0.05 1.02 +/- 0.00 27.51 28.11 +/- 0.03 0.98 +/- 0.00 18.72 18.55 +/- 0.02 1.01 +/- 0.00 15.84 15.89 +/- 0.05 1.00 +/- 0.00 8.943 8.89 +/- 0.04 1.01 +/- 0.00 3.935 3.98 +/- 0.04 0.99 +/- 0.01 B3086/3 0.2362 0.27 +/- 0.05 0.87 +/- 0.16 24.24 23.68 +/- 0.05 1.02 +/- 0.00 28.08 28.83 +/- 0.03 0.97 +/- 0.00 18.63 18.45 +/- 0.02 1.01 +/- 0.00 15.90 15.93 +/- 0.05 1.00 +/- 0.00 8.957 8.88 +/- 0.04 1.01 +/- 0.00 3.953 3.96 +/- 0.04 1.00 +/- 0.01 B3086/4 0.1893 0.26 +/- 0.01 0.73 +/- 0.03 25.40 24.74 +/- 0.01 1.03 +/- 0.00 26.81 27.54 +/- 0.01 0.97 +/- 0.00 18.87 18.68 +/- 0.01 1.01 +/- 0.00 15.84 15.88 +/- 0.01 1.00 +/- 0.00 8.958 8.91 +/- 0.01 1.01 +/- 0.00 3.928 4.00 +/- 0.01 0.98 +/- 0.00 B3086/5 0.2029 0.25 +/- 0.01 0.81 +/- 0.03 25.07 24.41 +/- 0.02 1.03 +/- 0.00 27.16 28.01 +/- 0.02 0.97 +/- 0.00 18.81 18.60 +/- 0.01 1.01 +/- 0.00 15.86 15.88 +/- 0.01 1.00 +/- 0.00 8.960 8.88 +/- 0.01 1.01 +/- 0.00 3.935 3.97 +/- 0.01 0.99 +/- 0.00 B3086/6 0.2272 0.25 +/- 0.01 0.91 +/- 0.04 24.50 23.76 +/- 0.01 1.03 +/- 0.00 27.72 28.61 +/- 0.01 0.97 +/- 0.00 18.72 18.51 +/- 0.01 1.01 +/- 0.00 15.91 15.95 +/- 0.01 1.00 +/- 0.00 8.969 8.92 +/- 0.01 1.01 +/- 0.00 3.950 4.00 +/- 0.01 0.99 +/- 0.00 C3139/1 0.2782 0.36 +/- 0.02 0.77 +/- 0.04 23.70 22.93 +/- 0.02 1.03 +/- 0.00 28.48 29.50 +/- 0.03 0.97 +/- 0.00 18.47 18.26 +/- 0.02 1.01 +/- 0.00 16.06 16.07 +/- 0.02 1.00 +/- 0.00 8.984 8.85 +/- 0.02 1.02 +/- 0.00 4.037 4.03 +/- 0.02 1.00 +/- 0.00 C3139/2 0.2977 0.40 +/- 0.02 0.74 +/- 0.04 23.28 22.29 +/- 0.02 1.04 +/- 0.00 28.87 29.92 +/- 0.03 0.97 +/- 0.00 18.41 18.21 +/- 0.02 1.01 +/- 0.00 16.10 16.20 +/- 0.02 0.99 +/- 0.00 8.993 8.92 +/- 0.02 1.01 +/- 0.00 4.050 4.08 +/- 0.02 0.99 +/- 0.00 C3139/3 0.3437 0.43 +/- 0.02 0.80 +/- 0.04 22.35 21.48 +/- 0.02 1.04 +/- 0.00 29.73 30.93 +/- 0.03 0.96 +/- 0.00 18.25 18.02 +/- 0.02 1.01 +/- 0.00 16.21 16.23 +/- 0.02 1.00 +/- 0.00 9.020 8.86 +/- 0.02 1.02 +/- 0.00 4.089 4.07 +/- 0.02 1.00 +/- 0.00 C3139/4 0.2769 0.15 +/- 0.05 1.85 +/- 0.62 23.55 22.95 +/- 0.01 1.03 +/- 0.00 28.93 29.94 +/- 0.01 0.97 +/- 0.00 18.35 18.19 +/- 0.01 1.01 +/- 0.00 15.96 15.98 +/- 0.01 1.00 +/- 0.00 8.928 8.80 +/- 0.01 1.01 +/- 0.00 4.013 3.99 +/- 0.01 1.01 +/- 0.00 C3139/5 0.2776 0.20 +/- 0.05 1.39 +/- 0.35 23.47 22.57 +/- 0.01 1.04 +/- 0.00 29.05 30.10 +/- 0.01 0.97 +/- 0.00 18.35 18.18 +/- 0.01 1.01 +/- 0.00 15.93 16.02 +/- 0.01 0.99 +/- 0.00 8.916 8.88 +/- 0.01 1.00 +/- 0.00 3.999 4.05 +/- 0.01 0.99 +/- 0.00 C3139/6 0.3422 0.22 +/- 0.05 1.56 +/- 0.35 22.20 21.49 +/- 0.01 1.03 +/- 0.00 30.18 31.42 +/- 0.01 0.96 +/- 0.00 18.13 17.95 +/- 0.01 1.01 +/- 0.00 16.11 16.12 +/- 0.01 1.00 +/- 0.00 8.965 8.80 +/- 0.01 1.02 +/- 0.00 4.065 4.00 +/- 0.01 1.02 +/- 0.00 B4175/1 0.3436 0.43 +/- 0.02 0.80 +/- 0.04 22.59 21.47 +/- 0.02 1.05 +/- 0.00 29.87 30.89 +/- 0.03 0.97 +/- 0.00 18.03 17.90 +/- 0.02 1.01 +/- 0.00 16.14 16.30 +/- 0.02 0.99 +/- 0.00 8.957 8.90 +/- 0.02 1.01 +/- 0.00 4.080 4.11 +/- 0.02 0.99 +/- 0.00 B4175/2 0.3696 0.44 +/- 0.02 0.84 +/- 0.04 22.04 20.85 +/- 0.02 1.06 +/- 0.00 30.39 31.49 +/- 0.03 0.96 +/- 0.00 17.94 17.80 +/- 0.02 1.01 +/- 0.00 16.19 16.37 +/- 0.02 0.99 +/- 0.00 8.968 8.92 +/- 0.02 1.01 +/- 0.00 4.096 4.13 +/- 0.02 0.99 +/- 0.00 B4175/3 0.4280 0.50 +/- 0.02 0.86 +/- 0.03 20.91 19.70 +/- 0.02 1.06 +/- 0.00 31.43 32.52 +/- 0.03 0.97 +/- 0.00 17.75 17.60 +/- 0.02 1.01 +/- 0.00 16.34 16.53 +/- 0.02 0.99 +/- 0.00 9.001 8.96 +/- 0.02 1.00 +/- 0.00 4.145 4.19 +/- 0.02 0.99 +/- 0.00 B4175/4 0.3316 0.37 +/- 0.02 0.90 +/- 0.05 22.66 21.40 +/- 0.02 1.06 +/- 0.00 30.06 31.18 +/- 0.02 0.96 +/- 0.00 17.97 17.82 +/- 0.02 1.01 +/- 0.00 16.02 16.19 +/- 0.02 0.99 +/- 0.00 8.902 8.85 +/- 0.01 1.01 +/- 0.00 4.047 4.10 +/- 0.01 0.99 +/- 0.00 B4175/5 0.3665 0.39 +/- 0.02 0.94 +/- 0.05 21.97 20.72 +/- 0.02 1.06 +/- 0.00 30.69 31.69 +/- 0.02 0.97 +/- 0.00 17.87 17.72 +/- 0.02 1.01 +/- 0.00 16.11 16.32 +/- 0.02 0.99 +/- 0.00 8.925 8.93 +/- 0.01 1.00 +/- 0.00 4.075 4.18 +/- 0.01 0.97 +/- 0.00 B4175/6 0.4286 0.46 +/- 0.02 0.93 +/- 0.04 20.78 19.62 +/- 0.02 1.06 +/- 0.00 31.75 32.73 +/- 0.02 0.97 +/- 0.00 17.66 17.50 +/- 0.02 1.01 +/- 0.00 16.28 16.46 +/- 0.02 0.99 +/- 0.00 8.964 8.94 +/- 0.01 1.00 +/- 0.00 4.130 4.18 +/- 0.01 0.99 +/- 0.00 B4180/1 0.3080 0.36 +/- 0.02 0.86 +/- 0.05 23.34 22.09 +/- 0.05 1.06 +/- 0.00 29.34 30.56 +/- 0.05 0.96 +/- 0.00 18.23 18.19 +/- 0.05 1.00 +/- 0.00 16.01 16.08 +/- 0.05 1.00 +/- 0.00 8.858 8.80 +/- 0.04 1.01 +/- 0.00 3.920 3.92 +/- 0.03 1.00 +/- 0.01
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 46 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Nd142/Nd (% a/a) Nd143/Nd (% a/a) Nd144/Nd (% a/a) Nd145/Nd (% a/a) Nd146/Nd (% a/a) Nd148/Nd (% a/a) Nd150/Nd (% a/a) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E B4180/2 0.2894 0.36 +/- 0.02 0.80 +/- 0.04 23.69 22.19 +/- 0.05 1.07 +/- 0.00 29.05 30.43 +/- 0.05 0.95 +/- 0.00 18.29 18.22 +/- 0.05 1.00 +/- 0.00 15.94 16.07 +/- 0.05 0.99 +/- 0.00 8.839 8.82 +/- 0.04 1.00 +/- 0.00 3.898 3.93 +/- 0.03 0.99 +/- 0.01 B4180/3 0.2839 0.33 +/- 0.02 0.86 +/- 0.05 23.80 22.64 +/- 0.05 1.05 +/- 0.00 28.96 30.05 +/- 0.05 0.96 +/- 0.00 18.31 18.29 +/- 0.05 1.00 +/- 0.00 15.92 15.99 +/- 0.05 1.00 +/- 0.00 8.834 8.79 +/- 0.04 1.00 +/- 0.00 3.891 3.91 +/- 0.03 1.00 +/- 0.01 B4180/4 0.3005 0.37 +/- 0.02 0.81 +/- 0.04 23.48 22.33 +/- 0.05 1.05 +/- 0.00 29.22 30.36 +/- 0.05 0.96 +/- 0.00 18.25 18.20 +/- 0.05 1.00 +/- 0.00 15.98 16.05 +/- 0.05 1.00 +/- 0.00 8.851 8.78 +/- 0.04 1.01 +/- 0.00 3.912 3.91 +/- 0.03 1.00 +/- 0.01 B4180/5 0.2912 0.35 +/- 0.02 0.83 +/- 0.05 23.66 22.55 +/- 0.05 1.05 +/- 0.00 29.08 30.19 +/- 0.05 0.96 +/- 0.00 18.29 18.25 +/- 0.05 1.00 +/- 0.00 15.95 16.00 +/- 0.05 1.00 +/- 0.00 8.841 8.76 +/- 0.04 1.01 +/- 0.00 3.900 3.90 +/- 0.03 1.00 +/- 0.01 B4180/6 0.2658 0.31 +/- 0.02 0.86 +/- 0.06 24.14 22.99 +/- 0.05 1.05 +/- 0.00 28.67 29.71 +/- 0.05 0.96 +/- 0.00 18.38 18.33 +/- 0.05 1.00 +/- 0.00 15.86 15.96 +/- 0.05 0.99 +/- 0.00 8.815 8.79 +/- 0.04 1.00 +/- 0.00 3.869 3.91 +/- 0.03 0.99 +/- 0.01 B4180/7 B4180/8 B4181/1 B4181/2 B4181/3 B4181/4 B3221/1 0.3622 0.43 +/- 0.02 0.84 +/- 0.04 22.38 21.07 +/- 0.02 1.06 +/- 0.00 29.84 31.02 +/- 0.03 0.96 +/- 0.00 18.06 17.93 +/- 0.02 1.01 +/- 0.00 16.28 16.47 +/- 0.02 0.99 +/- 0.00 9.001 8.97 +/- 0.02 1.00 +/- 0.00 4.065 4.11 +/- 0.02 0.99 +/- 0.00 B3221/2 0.3925 0.47 +/- 0.02 0.84 +/- 0.04 21.76 20.47 +/- 0.02 1.06 +/- 0.00 30.42 31.66 +/- 0.03 0.96 +/- 0.00 17.97 17.81 +/- 0.02 1.01 +/- 0.00 16.36 16.52 +/- 0.02 0.99 +/- 0.00 9.016 8.96 +/- 0.02 1.01 +/- 0.00 4.083 4.11 +/- 0.02 0.99 +/- 0.00 B3221/3 0.4449 0.55 +/- 0.02 0.81 +/- 0.03 20.74 19.38 +/- 0.02 1.07 +/- 0.00 31.36 32.65 +/- 0.03 0.96 +/- 0.00 17.80 17.62 +/- 0.02 1.01 +/- 0.00 16.49 16.66 +/- 0.02 0.99 +/- 0.00 9.050 8.99 +/- 0.02 1.01 +/- 0.00 4.126 4.15 +/- 0.02 0.99 +/- 0.00 B3221/4 0.3525 0.39 +/- 0.05 0.90 +/- 0.12 22.29 20.94 +/- 0.02 1.06 +/- 0.00 30.39 31.56 +/- 0.02 0.96 +/- 0.00 17.92 17.78 +/- 0.02 1.01 +/- 0.00 16.11 16.31 +/- 0.02 0.99 +/- 0.00 8.913 8.89 +/- 0.02 1.00 +/- 0.00 4.021 4.08 +/- 0.02 0.99 +/- 0.00 B3221/5 0.3713 0.49 +/- 0.05 0.76 +/- 0.08 21.87 20.24 +/- 0.02 1.08 +/- 0.00 30.79 32.00 +/- 0.02 0.96 +/- 0.00 17.87 17.58 +/- 0.02 1.02 +/- 0.00 16.15 16.30 +/- 0.02 0.99 +/- 0.00 8.917 8.84 +/- 0.02 1.01 +/- 0.00 4.027 4.06 +/- 0.02 0.99 +/- 0.00 B3221/6 0.4270 0.49 +/- 0.05 0.87 +/- 0.09 20.79 19.24 +/- 0.02 1.08 +/- 0.00 31.78 33.10 +/- 0.02 0.96 +/- 0.00 17.69 17.48 +/- 0.02 1.01 +/- 0.00 16.29 16.53 +/- 0.02 0.99 +/- 0.00 8.956 8.93 +/- 0.02 1.00 +/- 0.00 4.075 4.14 +/- 0.02 0.98 +/- 0.00 B4259/1 0.4159 0.49 +/- 0.02 0.85 +/- 0.03 21.23 19.77 +/- 0.04 1.07 +/- 0.00 31.26 32.47 +/- 0.05 0.96 +/- 0.00 17.69 17.57 +/- 0.04 1.01 +/- 0.00 16.30 16.53 +/- 0.04 0.99 +/- 0.00 8.977 8.98 +/- 0.03 1.00 +/- 0.00 4.121 4.19 +/- 0.02 0.98 +/- 0.00 B4259/2 0.4450 0.48 +/- 0.02 0.93 +/- 0.04 20.65 19.14 +/- 0.04 1.08 +/- 0.00 31.80 33.11 +/- 0.05 0.96 +/- 0.00 17.61 17.44 +/- 0.04 1.01 +/- 0.00 16.37 16.62 +/- 0.04 0.98 +/- 0.00 8.990 9.00 +/- 0.03 1.00 +/- 0.00 4.137 4.21 +/- 0.02 0.98 +/- 0.00 B4259/3 0.5090 0.57 +/- 0.02 0.89 +/- 0.03 19.48 17.92 +/- 0.04 1.09 +/- 0.00 32.84 34.14 +/- 0.05 0.96 +/- 0.00 17.40 17.28 +/- 0.04 1.01 +/- 0.00 16.53 16.78 +/- 0.04 0.99 +/- 0.00 9.033 9.03 +/- 0.03 1.00 +/- 0.00 4.193 4.28 +/- 0.02 0.98 +/- 0.00 B4259/4 0.4179 0.48 +/- 0.01 0.87 +/- 0.02 21.17 19.63 +/- 0.02 1.08 +/- 0.00 31.36 32.73 +/- 0.02 0.96 +/- 0.00 17.67 17.51 +/- 0.02 1.01 +/- 0.00 16.29 16.54 +/- 0.02 0.99 +/- 0.00 8.971 8.92 +/- 0.02 1.01 +/- 0.00 4.120 4.19 +/- 0.02 0.98 +/- 0.00 B4259/5 0.4495 0.48 +/- 0.01 0.94 +/- 0.02 20.55 19.05 +/- 0.02 1.08 +/- 0.00 31.93 33.35 +/- 0.02 0.96 +/- 0.00 17.58 17.42 +/- 0.02 1.01 +/- 0.00 16.37 16.61 +/- 0.02 0.99 +/- 0.00 8.986 8.90 +/- 0.02 1.01 +/- 0.00 4.139 4.18 +/- 0.02 0.99 +/- 0.00 B4259/6 0.5188 0.55 +/- 0.01 0.94 +/- 0.02 19.30 17.88 +/- 0.02 1.08 +/- 0.00 33.04 34.31 +/- 0.02 0.96 +/- 0.00 17.36 17.20 +/- 0.02 1.01 +/- 0.00 16.55 16.76 +/- 0.02 0.99 +/- 0.00 9.034 8.98 +/- 0.02 1.01 +/- 0.00 4.200 4.33 +/- 0.02 0.97 +/- 0.00 B3284/1 0.5112 0.66 +/- 0.02 0.77 +/- 0.02 19.59 17.94 +/- 0.10 1.09 +/- 0.01 32.83 34.18 +/- 0.10 0.96 +/- 0.00 17.32 17.17 +/- 0.10 1.01 +/- 0.01 16.54 16.80 +/- 0.10 0.98 +/- 0.01 9.004 8.98 +/- 0.05 1.00 +/- 0.01 4.201 4.26 +/- 0.03 0.99 +/- 0.01 B3284/2 0.5436 0.63 +/- 0.02 0.86 +/- 0.03 19.00 17.29 +/- 0.10 1.10 +/- 0.01 33.38 34.92 +/- 0.10 0.96 +/- 0.00 17.23 17.04 +/- 0.10 1.01 +/- 0.01 16.61 16.89 +/- 0.10 0.98 +/- 0.01 9.017 8.97 +/- 0.05 1.01 +/- 0.01 4.218 4.26 +/- 0.03 0.99 +/- 0.01 B3284/3 0.6263 0.74 +/- 0.02 0.85 +/- 0.02 17.65 16.08 +/- 0.10 1.10 +/- 0.01 34.56 35.91 +/- 0.10 0.96 +/- 0.00 16.98 16.80 +/- 0.10 1.01 +/- 0.01 16.83 17.10 +/- 0.10 0.98 +/- 0.01 9.071 9.03 +/- 0.05 1.00 +/- 0.01 4.289 4.34 +/- 0.03 0.99 +/- 0.01 B3284/4 0.5050 0.60 +/- 0.01 0.84 +/- 0.01 19.63 17.89 +/- 0.02 1.10 +/- 0.00 32.91 34.30 +/- 0.02 0.96 +/- 0.00 17.30 17.11 +/- 0.02 1.01 +/- 0.00 16.49 16.71 +/- 0.02 0.99 +/- 0.00 8.981 8.98 +/- 0.02 1.00 +/- 0.00 4.187 4.26 +/- 0.02 0.98 +/- 0.00 B3284/5 0.5532 0.68 +/- 0.01 0.81 +/- 0.01 18.79 17.21 +/- 0.02 1.09 +/- 0.00 33.66 35.00 +/- 0.02 0.96 +/- 0.00 17.16 16.99 +/- 0.02 1.01 +/- 0.00 16.61 16.86 +/- 0.02 0.99 +/- 0.00 9.006 8.98 +/- 0.02 1.00 +/- 0.00 4.219 4.28 +/- 0.02 0.99 +/- 0.00 B3284/6 0.6250 0.70 +/- 0.02 0.89 +/- 0.03 17.62 16.05 +/- 0.02 1.10 +/- 0.00 34.69 36.07 +/- 0.02 0.96 +/- 0.00 16.94 16.77 +/- 0.02 1.01 +/- 0.00 16.79 17.04 +/- 0.02 0.99 +/- 0.00 9.052 9.02 +/- 0.02 1.00 +/- 0.00 4.281 4.35 +/- 0.02 0.98 +/- 0.00 B3362/1 0.3246 0.36 +/- 0.05 0.90 +/- 0.13 22.74 21.64 +/- 0.05 1.05 +/- 0.00 30.41 31.14 +/- 0.05 0.98 +/- 0.00 17.90 17.82 +/- 0.05 1.00 +/- 0.00 15.94 16.19 +/- 0.05 0.98 +/- 0.00 8.788 8.84 +/- 0.04 0.99 +/- 0.00 3.903 4.01 +/- 0.03 0.97 +/- 0.01 B3362/2 0.3516 0.40 +/- 0.06 0.88 +/- 0.13 22.15 21.08 +/- 0.05 1.05 +/- 0.00 30.95 31.73 +/- 0.05 0.98 +/- 0.00 17.82 17.70 +/- 0.05 1.01 +/- 0.00 16.00 16.24 +/- 0.05 0.99 +/- 0.00 8.800 8.83 +/- 0.04 1.00 +/- 0.00 3.917 4.02 +/- 0.03 0.97 +/- 0.01 B3362/3 0.4077 0.45 +/- 0.07 0.91 +/- 0.14 21.03 19.96 +/- 0.05 1.05 +/- 0.00 31.98 32.77 +/- 0.05 0.98 +/- 0.00 17.64 17.52 +/- 0.05 1.01 +/- 0.00 16.15 16.38 +/- 0.05 0.99 +/- 0.00 8.835 8.86 +/- 0.04 1.00 +/- 0.00 3.960 4.06 +/- 0.03 0.98 +/- 0.01 B3362/4 0.3268 0.34 +/- 0.02 0.96 +/- 0.06 22.67 21.45 +/- 0.08 1.06 +/- 0.00 30.51 31.55 +/- 0.02 0.97 +/- 0.00 17.88 17.78 +/- 0.02 1.01 +/- 0.00 15.93 16.15 +/- 0.02 0.99 +/- 0.00 8.782 8.71 +/- 0.02 1.01 +/- 0.00 3.902 4.07 +/- 0.01 0.96 +/- 0.00 B3362/5 0.3452 0.32 +/- 0.03 1.08 +/- 0.10 22.24 20.88 +/- 0.04 1.07 +/- 0.00 30.93 32.24 +/- 0.08 0.96 +/- 0.00 17.83 17.68 +/- 0.04 1.01 +/- 0.00 15.97 16.18 +/- 0.02 0.99 +/- 0.00 8.785 8.66 +/- 0.02 1.01 +/- 0.00 3.905 4.04 +/- 0.02 0.97 +/- 0.00 B3362/6 0.4127 0.38 +/- 0.01 1.09 +/- 0.03 20.92 19.72 +/- 0.02 1.06 +/- 0.00 32.12 33.18 +/- 0.01 0.97 +/- 0.00 17.60 17.45 +/- 0.04 1.01 +/- 0.00 16.16 16.41 +/- 0.05 0.98 +/- 0.00 8.832 8.73 +/- 0.01 1.01 +/- 0.00 3.962 4.14 +/- 0.02 0.96 +/- 0.00 Mean ; SD 0.83 ; 0.30 1.05 ; 0.03 0.97 ; 0.01 1.008 ; 0.004 0.99 ; 0.01 1.01 ; 0.01 0.99 ; 0.01
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 47 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 12: AGR results for the neodymium isotopes (with respect to uranium).14
Nd142/U (1E-6 g/g) Nd143/U (1E-6 g/g) Nd144/U (1E-6 g/g) Nd145/U (1E-6 g/g) Nd146/U (1E-6 g/g) Nd150/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E B4001/1 1.805E-2 3.38E-1 0.05 4.081E1 4.06E1 1.01 2.945E1 3.00E1 0.98 2.757E1 2.75E1 1.00 2.144E1 2.16E1 0.99 5.087E0 5.29E0 0.96 B4001/2 2.278E-2 2.91E-1 0.08 4.601E1 4.56E1 1.01 3.406E1 3.43E1 0.99 3.111E1 3.12E1 1.00 2.421E1 2.46E1 0.98 5.737E0 5.92E0 0.97 B4001/3 2.906E-2 2.09E-1 0.14 5.232E1 5.19E1 1.01 3.893E1 3.95E1 0.99 3.538E1 3.55E1 1.00 2.751E1 2.79E1 0.99 6.484E0 6.62E0 0.98 B4001/4 2.880E-2 8.54E-2 0.34 5.130E1 5.07E1 1.01 3.812E1 3.88E1 0.98 3.476E1 3.49E1 1.00 2.711E1 2.74E1 0.99 6.456E0 6.48E0 1.00 B4001/5 3.346E-2 1.67E-1 0.20 5.552E1 5.54E1 1.00 4.139E1 4.24E1 0.98 3.764E1 3.79E1 0.99 2.936E1 2.97E1 0.99 6.981E0 7.03E0 0.99 B4001/6 3.798E-2 1.19E-1 0.32 5.961E1 5.92E1 1.01 4.460E1 4.55E1 0.98 4.040E1 4.06E1 0.99 3.146E1 3.18E1 0.99 7.434E0 7.51E0 0.99 B4040/1 9.908E-1 1.70E0 0.58 1.964E2 2.08E2 0.94 1.888E2 2.03E2 0.93 1.440E2 1.50E2 0.96 1.189E2 1.25E2 0.95 3.054E1 3.13E1 0.98 B4040/2 1.017E0 1.81E0 0.56 1.991E2 2.00E2 0.99 1.923E2 1.98E2 0.97 1.462E2 1.47E2 0.99 1.207E2 1.23E2 0.98 3.095E1 3.11E1 0.99 B4040/3 1.309E0 1.99E0 0.66 2.220E2 2.23E2 0.99 2.217E2 2.35E2 0.94 1.652E2 1.66E2 1.00 1.371E2 1.43E2 0.96 3.526E1 3.56E1 0.99 B4040/4 9.378E-1 1.51E0 0.62 1.918E2 1.90E2 1.01 1.787E2 1.88E2 0.95 1.403E2 1.40E2 1.00 1.156E2 1.17E2 0.99 2.967E1 3.02E1 0.98 B4040/5 1.050E0 9.85E-1 1.07 2.018E2 1.99E2 1.02 1.906E2 1.99E2 0.96 1.484E2 1.48E2 1.00 1.226E2 1.24E2 0.99 3.147E1 3.19E1 0.99 B4040/6 1.378E0 1.47E0 0.93 2.267E2 2.23E2 1.02 2.222E2 2.32E2 0.96 1.691E2 1.68E2 1.00 1.407E2 1.42E2 0.99 3.622E1 3.68E1 0.98 B4040/7 1.318E0 1.81E0 0.73 2.212E2 2.23E2 0.99 2.196E2 2.32E2 0.95 1.644E2 1.67E2 0.99 1.371E2 1.40E2 0.98 3.547E1 3.56E1 1.00 B4040/8 1.434E0 2.15E0 0.67 2.295E2 2.31E2 0.99 2.308E2 2.41E2 0.96 1.714E2 1.73E2 0.99 1.432E2 1.45E2 0.99 3.706E1 3.72E1 1.00 B4040/9 1.638E0 2.19E0 0.75 2.431E2 2.68E2 0.91 2.499E2 2.62E2 0.95 1.831E2 1.93E2 0.95 1.533E2 1.61E2 0.95 3.967E1 4.03E1 0.98 B3065/1 1.372E0 1.60E0 0.86 2.521E2 2.48E2 1.02 2.334E2 2.43E2 0.96 1.852E2 1.84E2 1.00 1.534E2 1.55E2 0.99 3.868E1 3.99E1 0.97 B3065/2 1.620E0 1.44E0 1.12 2.708E2 2.67E2 1.01 2.627E2 2.74E2 0.96 2.007E2 2.00E2 1.00 1.670E2 1.69E2 0.99 4.213E1 4.29E1 0.98 B3065/3 2.090E0 1.28E0 1.63 3.013E2 2.97E2 1.02 3.040E2 3.18E2 0.96 2.267E2 2.26E2 1.00 1.899E2 1.92E2 0.99 4.796E1 4.89E1 0.98 B3086/1 2.468E0 3.93E0 0.63 3.173E2 3.17E2 1.00 3.459E2 3.58E2 0.97 2.401E2 2.41E2 1.00 2.038E2 2.06E2 0.99 5.200E1 5.24E1 0.99 B3086/2 2.796E0 4.16E0 0.67 3.333E2 3.28E2 1.02 3.717E2 3.82E2 0.97 2.548E2 2.54E2 1.00 2.171E2 2.19E2 0.99 5.540E1 5.64E1 0.98 B3086/3 3.517E0 4.06E0 0.87 3.635E2 3.58E2 1.01 4.241E2 4.39E2 0.97 2.833E2 2.83E2 1.00 2.434E2 2.46E2 0.99 6.220E1 6.29E1 0.99 B3086/4 2.276E0 3.14E0 0.72 3.075E2 3.01E2 1.02 3.268E2 3.38E2 0.97 2.316E2 2.31E2 1.00 1.958E2 1.97E2 0.99 4.989E1 5.11E1 0.98 B3086/5 2.612E0 3.25E0 0.80 3.249E2 3.19E2 1.02 3.546E2 3.69E2 0.96 2.473E2 2.47E2 1.00 2.100E2 2.12E2 0.99 5.352E1 5.45E1 0.98 B3086/6 3.257E0 3.61E0 0.90 3.538E2 3.45E2 1.03 4.031E2 4.18E2 0.96 2.740E2 2.73E2 1.01 2.345E2 2.37E2 0.99 5.982E1 6.09E1 0.98 C3139/1 4.565E0 6.00E0 0.76 3.915E2 3.85E2 1.02 4.738E2 4.98E2 0.95 3.093E2 3.11E2 1.00 2.708E2 2.75E2 0.98 6.997E1 7.09E1 0.99 C3139/2 5.186E0 7.03E0 0.74 4.084E2 3.94E2 1.04 5.101E2 5.33E2 0.96 3.275E2 3.27E2 1.00 2.884E2 2.93E2 0.99 7.453E1 7.58E1 0.98 C3139/3 6.771E0 8.63E0 0.78 4.434E2 4.34E2 1.02 5.940E2 6.29E2 0.94 3.671E2 3.69E2 0.99 3.284E2 3.35E2 0.98 8.510E1 8.63E1 0.99 C3139/4 4.576E0 2.52E0 1.82 3.919E2 3.88E2 1.01 4.849E2 5.09E2 0.95 3.097E2 3.12E2 0.99 2.712E2 2.76E2 0.98 7.006E1 7.07E1 0.99 C3139/5 4.622E0 3.34E0 1.38 3.934E2 3.80E2 1.03 4.904E2 5.11E2 0.96 3.120E2 3.10E2 1.00 2.727E2 2.75E2 0.99 7.034E1 7.16E1 0.98 C3139/6 6.794E0 4.45E0 1.53 4.438E2 4.38E2 1.01 6.076E2 6.45E2 0.94 3.676E2 3.71E2 0.99 3.289E2 3.35E2 0.98 8.525E1 8.55E1 1.00 B4175/1 6.841E0 8.62E0 0.79 4.530E2 4.34E2 1.04 6.031E2 6.28E2 0.96 3.665E2 3.66E2 1.00 3.303E2 3.36E2 0.98 8.582E1 8.71E1 0.99 B4175/2 7.823E0 9.37E0 0.83 4.699E2 4.47E2 1.05 6.523E2 6.80E2 0.96 3.879E2 3.87E2 1.00 3.525E2 3.58E2 0.98 9.160E1 9.29E1 0.99 B4175/3 1.021E1 1.20E1 0.85 5.026E2 4.76E2 1.06 7.605E2 7.91E2 0.96 4.325E2 4.31E2 1.00 4.009E2 4.08E2 0.98 1.045E2 1.06E2 0.98 B4175/4 6.474E0 7.27E0 0.89 4.456E2 4.24E2 1.05 5.953E2 6.21E2 0.96 3.584E2 3.58E2 1.00 3.217E2 3.27E2 0.98 8.349E1 8.51E1 0.98 B4175/5 7.772E0 8.27E0 0.94 4.691E2 4.43E2 1.06 6.600E2 6.82E2 0.97 3.869E2 3.84E2 1.01 3.513E2 3.56E2 0.99 9.130E1 9.37E1 0.97
14 Derived in this work using the isotopic ratios with respect to neodymium and the Nd148/U ratio. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 48 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Nd142/U (1E-6 g/g) Nd143/U (1E-6 g/g) Nd144/U (1E-6 g/g) Nd145/U (1E-6 g/g) Nd146/U (1E-6 g/g) Nd150/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E B4175/6 1.031E1 1.11E1 0.93 5.037E2 4.77E2 1.06 7.750E2 8.01E2 0.97 4.341E2 4.31E2 1.01 4.028E2 4.09E2 0.99 1.050E2 1.07E2 0.98 B4180/1 6.668E0 7.85E0 0.85 5.089E2 4.85E2 1.05 6.442E2 6.76E2 0.95 4.030E2 4.05E2 0.99 3.563E2 3.61E2 0.99 8.967E1 9.03E1 0.99 B4180/2 5.965E0 7.44E0 0.80 4.917E2 4.62E2 1.06 6.072E2 6.38E2 0.95 3.850E2 3.85E2 1.00 3.379E2 3.41E2 0.99 8.488E1 8.58E1 0.99 B4180/3 5.762E0 6.74E0 0.86 4.864E2 4.65E2 1.05 5.961E2 6.22E2 0.96 3.796E2 3.81E2 1.00 3.323E2 3.36E2 0.99 8.344E1 8.43E1 0.99 B4180/4 6.380E0 7.92E0 0.81 5.021E2 4.82E2 1.04 6.293E2 6.59E2 0.95 3.958E2 3.98E2 0.99 3.489E2 3.53E2 0.99 8.774E1 8.85E1 0.99 B4180/5 6.033E0 7.32E0 0.82 4.935E2 4.75E2 1.04 6.108E2 6.40E2 0.95 3.868E2 3.90E2 0.99 3.397E2 3.44E2 0.99 8.536E1 8.62E1 0.99 B4180/6 5.118E0 5.99E0 0.85 4.681E2 4.47E2 1.05 5.598E2 5.82E2 0.96 3.613E2 3.62E2 1.00 3.140E2 3.17E2 0.99 7.869E1 7.98E1 0.99 B4180/7 B4180/8 B4181/1 B4181/2 B4181/3 B4181/4 B3221/1 7.949E0 9.47E0 0.84 4.946E2 4.68E2 1.06 6.640E2 6.93E2 0.96 4.048E2 4.03E2 1.00 3.674E2 3.73E2 0.98 9.425E1 9.57E1 0.99 B3221/2 9.184E0 1.11E1 0.83 5.127E2 4.86E2 1.06 7.217E2 7.56E2 0.95 4.294E2 4.28E2 1.00 3.934E2 4.00E2 0.98 1.009E2 1.02E2 0.99 B3221/3 1.150E1 1.43E1 0.80 5.398E2 5.08E2 1.06 8.221E2 8.62E2 0.95 4.699E2 4.69E2 1.00 4.383E2 4.46E2 0.98 1.127E2 1.14E2 0.99 B3221/4 7.697E0 8.54E0 0.90 4.902E2 4.62E2 1.06 6.729E2 7.01E2 0.96 3.996E2 3.98E2 1.00 3.618E2 3.67E2 0.98 9.276E1 9.44E1 0.98 B3221/5 8.463E0 1.13E1 0.75 5.021E2 4.69E2 1.07 7.118E2 7.47E2 0.95 4.159E2 4.13E2 1.01 3.784E2 3.86E2 0.98 9.696E1 9.87E1 0.98 B3221/6 1.088E1 1.25E1 0.87 5.334E2 4.95E2 1.08 8.212E2 8.58E2 0.96 4.602E2 4.56E2 1.01 4.269E2 4.35E2 0.98 1.097E2 1.12E2 0.98 B4259/1 9.726E0 1.15E1 0.85 5.000E2 4.66E2 1.07 7.414E2 7.70E2 0.96 4.225E2 4.20E2 1.01 3.920E2 3.98E2 0.99 1.018E2 1.04E2 0.98 B4259/2 1.096E1 1.18E1 0.93 5.124E2 4.75E2 1.08 7.945E2 8.27E2 0.96 4.430E2 4.39E2 1.01 4.146E2 4.21E2 0.99 1.077E2 1.10E2 0.98 B4259/3 1.394E1 1.56E1 0.89 5.373E2 4.95E2 1.09 9.120E2 9.49E2 0.96 4.867E2 4.84E2 1.01 4.654E2 4.73E2 0.98 1.213E2 1.24E2 0.98 B4259/4 9.826E0 1.14E1 0.87 5.013E2 4.68E2 1.07 7.476E2 7.85E2 0.95 4.242E2 4.23E2 1.00 3.939E2 4.02E2 0.98 1.023E2 1.05E2 0.98 B4259/5 1.117E1 1.21E1 0.93 5.145E2 4.82E2 1.07 8.049E2 8.49E2 0.95 4.462E2 4.47E2 1.00 4.183E2 4.29E2 0.98 1.087E2 1.11E2 0.98 B4259/6 1.443E1 1.54E1 0.94 5.406E2 5.04E2 1.07 9.316E2 9.74E2 0.96 4.928E2 4.92E2 1.00 4.732E2 4.82E2 0.98 1.234E2 1.28E2 0.96 B3284/1 1.393E1 1.81E1 0.77 5.378E2 4.94E2 1.09 9.076E2 9.48E2 0.96 4.820E2 4.80E2 1.01 4.636E2 4.72E2 0.98 1.210E2 1.23E2 0.98 B3284/2 1.549E1 1.81E1 0.86 5.451E2 4.99E2 1.09 9.647E2 1.02E3 0.95 5.014E2 4.99E2 1.01 4.867E2 4.98E2 0.98 1.270E2 1.29E2 0.98 B3284/3 1.986E1 2.36E1 0.84 5.637E2 5.16E2 1.09 1.111E3 1.16E3 0.96 5.497E2 5.47E2 1.01 5.486E2 5.60E2 0.98 1.437E2 1.46E2 0.98 B3284/4 1.369E1 1.63E1 0.84 5.361E2 4.89E2 1.10 9.049E2 9.44E2 0.96 4.789E2 4.74E2 1.01 4.597E2 4.66E2 0.99 1.200E2 1.22E2 0.98 B3284/5 1.602E1 1.98E1 0.81 5.481E2 5.04E2 1.09 9.883E2 1.03E3 0.96 5.074E2 5.04E2 1.01 4.945E2 5.04E2 0.98 1.291E2 1.31E2 0.98 B3284/6 1.986E1 2.23E1 0.89 5.637E2 5.16E2 1.09 1.118E3 1.17E3 0.96 5.497E2 5.46E2 1.01 5.486E2 5.59E2 0.98 1.437E2 1.47E2 0.98 B3362/1 7.563E0 8.35E0 0.91 5.336E2 5.05E2 1.06 7.185E2 7.32E2 0.98 4.260E2 4.22E2 1.01 3.819E2 3.86E2 0.99 9.608E1 9.82E1 0.98 B3362/2 8.737E0 9.91E0 0.88 5.544E2 5.26E2 1.05 7.801E2 7.97E2 0.98 4.523E2 4.48E2 1.01 4.089E2 4.14E2 0.99 1.028E2 1.05E2 0.98 B3362/3 1.139E1 1.25E1 0.91 5.916E2 5.60E2 1.06 9.059E2 9.26E2 0.98 5.031E2 4.99E2 1.01 4.639E2 4.69E2 0.99 1.169E2 1.20E2 0.98 B3362/4 7.671E0 8.05E0 0.95 5.358E2 5.12E2 1.05 7.261E2 7.58E2 0.96 4.285E2 4.30E2 1.00 3.845E2 3.93E2 0.98 9.676E1 1.02E2 0.95 B3362/5 8.476E0 7.98E0 1.06 5.501E2 5.24E2 1.05 7.701E2 8.15E2 0.95 4.470E2 4.50E2 0.99 4.031E2 4.15E2 0.97 1.013E2 1.06E2 0.95 B3362/6 1.165E1 1.09E1 1.07 5.946E2 5.67E2 1.05 9.192E2 9.61E2 0.96 5.074E2 5.09E2 1.00 4.688E2 4.82E2 0.97 1.181E2 1.25E2 0.95 Mean ; SD 0.82 ; 0.30 1.04 ; 0.04 0.96 ; 0.01 1.00 ; 0.01 0.98 ; 0.01 0.98 ; 0.01
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 49 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 13: AGR results for Nd148, plutonium and minor actinides.
Nd148/U (1E-5 g/g) Pu/U (1E-3 g/g) Am241/U (1E-5 g/g) Cm242/U (1E-7 g/g) Cm244/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E B4001/1 1.240 1.24 +/- 0.01 1.00 +/- 0.01 0.5672 0.521 +/- 0.005 1.09 +/- 0.01 B4001/2 1.400 1.40 +/- 0.06 1.00 +/- 0.04 0.6321 0.569 +/- 0.020 1.11 +/- 0.04 B4001/3 1.590 1.59 +/- 0.20 1.00 +/- 0.13 0.7154 0.703 +/- 0.050 1.02 +/- 0.07 B4001/4 1.570 1.57 +/- 0.02 1.00 +/- 0.01 0.7050 0.660 +/- 0.006 1.07 +/- 0.01 B4001/5 1.700 1.70 +/- 0.02 1.00 +/- 0.01 0.7552 0.688 +/- 0.006 1.10 +/- 0.01 B4001/6 1.820 1.82 +/- 0.03 1.00 +/- 0.02 0.8089 0.730 +/- 0.008 1.11 +/- 0.01 B4040/1 6.903 6.903 +/- 0.069 1.00 +/- 0.01 2.717 2.709 +/- 0.027 1.00 +/- 0.01 B4040/2 7.005 7.005 +/- 0.070 1.00 +/- 0.01 2.750 2.717 +/- 0.027 1.01 +/- 0.01 B4040/3 7.955 7.955 +/- 0.080 1.00 +/- 0.01 3.039 3.070 +/- 0.031 0.99 +/- 0.01 B4040/4 6.716 6.716 +/- 0.017 1.00 +/- 0.00 2.663 2.612 +/- 0.003 1.02 +/- 0.00 B4040/5 7.117 7.117 +/- 0.018 1.00 +/- 0.00 2.783 2.729 +/- 0.003 1.02 +/- 0.00 B4040/6 8.161 8.161 +/- 0.020 1.00 +/- 0.00 3.095 3.050 +/- 0.003 1.01 +/- 0.00 B4040/7 7.957 7.958 +/- 0.080 1.00 +/- 0.01 3.011 3.047 +/- 0.030 0.99 +/- 0.01 B4040/8 8.310 8.311 +/- 0.083 1.00 +/- 0.01 3.109 3.114 +/- 0.031 1.00 +/- 0.01 B4040/9 8.893 8.893 +/- 0.089 1.00 +/- 0.01 3.284 3.306 +/- 0.030 0.99 +/- 0.01 B3065/1 8.833 8.833 +/- 0.023 1.00 +/- 0.00 2.978 3.097 +/- 0.008 0.96 +/- 0.00 B3065/2 9.607 9.607 +/- 0.033 1.00 +/- 0.00 3.155 3.241 +/- 0.010 0.97 +/- 0.00 B3065/3 10.91 10.91 +/- 0.010 1.00 +/- 0.00 3.456 3.608 +/- 0.010 0.96 +/- 0.00 B3086/1 11.68 11.68 +/- 0.02 1.00 +/- 0.00 3.638 3.47 +/- 0.03 1.05 +/- 0.01 2.037 1.82 +/- 0.05 1.12 +/- 0.03 2.547 2.41 +/- 0.05 1.06 +/- 0.02 0.1897 0.215 +/- 0.010 0.88 +/- 0.04 B3086/2 12.43 12.43 +/- 0.02 1.00 +/- 0.00 3.783 3.60 +/- 0.04 1.05 +/- 0.01 2.160 2.19 +/- 0.05 0.99 +/- 0.02 2.797 2.87 +/- 0.05 0.97 +/- 0.02 0.2246 0.254 +/- 0.010 0.88 +/- 0.03 B3086/3 13.91 13.91 +/- 0.02 1.00 +/- 0.00 4.078 4.06 +/- 0.04 1.00 +/- 0.01 2.746 3.04 +/- 0.10 0.90 +/- 0.03 3.811 4.25 +/- 0.05 0.90 +/- 0.01 0.3580 0.398 +/- 0.020 0.90 +/- 0.05 B3086/4 11.23 11.23 +/- 0.03 1.00 +/- 0.00 3.541 3.487 +/- 0.002 1.02 +/- 0.00 1.924 1.75 1.10 2.300 2.10 1.10 0.1558 0.148 1.05 B3086/5 12.03 12.03 +/- 0.02 1.00 +/- 0.00 3.700 3.624 +/- 0.005 1.02 +/- 0.00 2.060 2.05 1.00 2.571 2.57 1.00 0.1908 0.169 1.13 B3086/6 13.41 13.41 +/- 0.01 1.00 +/- 0.00 3.981 3.962 +/- 0.003 1.00 +/- 0.00 2.608 2.55 1.02 3.468 3.52 0.99 0.2972 0.274 1.08 C3139/1 15.37 15.37 +/- 0.05 1.00 +/- 0.00 4.392 4.37 +/- 0.04 1.01 +/- 0.01 3.483 3.86 +/- 0.50 0.90 +/- 0.12 11.84 11.9 +/- 0.5 0.99 +/- 0.04 0.7543 0.93 +/- 0.40 0.81 +/- 0.35 C3139/2 16.34 16.34 +/- 0.07 1.00 +/- 0.00 4.553 4.48 +/- 0.04 1.02 +/- 0.01 3.632 3.44 +/- 0.74 1.06 +/- 0.23 13.15 14.1 +/- 0.2 0.93 +/- 0.01 0.8941 1.15 +/- 0.13 0.78 +/- 0.09 C3139/3 18.53 18.53 +/- 0.07 1.00 +/- 0.00 4.926 4.93 +/- 0.05 1.00 +/- 0.01 4.469 4.20 +/- 0.73 1.06 +/- 0.18 18.75 20.1 +/- 0.3 0.93 +/- 0.01 1.573 2.16 +/- 0.10 0.73 +/- 0.03 C3139/4 15.39 15.39 +/- 0.05 1.00 +/- 0.00 4.392 4.295 +/- 0.010 1.02 +/- 0.00 3.487 3.98 0.88 11.87 11.2 1.06 0.7586 0.74 1.03 C3139/5 15.48 15.48 +/- 0.05 1.00 +/- 0.00 4.390 4.273 +/- 0.010 1.03 +/- 0.00 3.414 3.96 0.86 11.58 10.8 1.07 0.6861 0.78 0.88 C3139/6 18.56 18.56 +/- 0.10 1.00 +/- 0.01 4.925 4.840 +/- 0.010 1.02 +/- 0.00 4.476 5.41 0.83 18.82 18.7 1.01 1.585 1.66 0.96 B4175/1 18.60 18.6 +/- 0.2 1.00 +/- 0.01 4.943 4.87 +/- 0.05 1.01 +/- 0.01 4.711 4.19 +/- 0.83 1.12 +/- 0.22 7.933 9.40 +/- 0.20 0.84 +/- 0.02 1.856 2.24 +/- 0.13 0.83 +/- 0.05 B4175/2 19.80 19.8 +/- 0.3 1.00 +/- 0.02 5.116 5.03 +/- 0.05 1.02 +/- 0.01 4.934 5.76 +/- 0.98 0.86 +/- 0.15 8.705 10.60 +/- 0.20 0.82 +/- 0.02 2.224 3.17 +/- 0.02 0.70 +/- 0.00 B4175/3 22.40 22.4 +/- 0.2 1.00 +/- 0.01 5.500 5.47 +/- 0.05 1.01 +/- 0.01 5.921 8.35 +/- 0.86 0.71 +/- 0.07 12.20 15.00 +/- 0.20 0.81 +/- 0.01 3.916 5.17 +/- 0.02 0.76 +/- 0.00 B4175/4 18.13 18.13 +/- 0.05 1.00 +/- 0.00 4.857 4.606 +/- 0.010 1.05 +/- 0.00 5.282 5.22 +/- 0.18 1.01 +/- 0.03 4.212 4.55 +/- 0.04 0.93 +/- 0.01 1.620 2.00 +/- 0.03 0.81 +/- 0.01 B4175/5 19.74 19.74 +/- 0.05 1.00 +/- 0.00 5.101 4.773 +/- 0.010 1.07 +/- 0.00 5.658 6.11 +/- 0.11 0.93 +/- 0.02 4.915 5.34 +/- 0.05 0.92 +/- 0.01 2.161 2.80 +/- 0.04 0.77 +/- 0.01 B4175/6 22.50 22.50 +/- 0.05 1.00 +/- 0.00 5.508 5.178 +/- 0.010 1.06 +/- 0.00 6.867 7.18 +/- 0.09 0.96 +/- 0.01 6.993 7.33 +/- 0.07 0.95 +/- 0.01 3.947 4.76 +/- 0.05 0.83 +/- 0.01 B4180/1 20.00 20.0 +/- 0.2 1.00 +/- 0.01 4.843 4.59 +/- 0.05 1.06 +/- 0.01
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Nd148/U (1E-5 g/g) Pu/U (1E-3 g/g) Am241/U (1E-5 g/g) Cm242/U (1E-7 g/g) Cm244/U (1E-6 g/g) C E C/E C E C/E C E C/E C E C/E C E C/E B4180/2 19.00 19.0 +/- 0.2 1.00 +/- 0.01 4.686 4.52 +/- 0.05 1.04 +/- 0.01 B4180/3 18.70 18.7 +/- 0.2 1.00 +/- 0.01 4.637 4.35 +/- 0.04 1.07 +/- 0.01 B4180/4 19.60 19.6 +/- 0.2 1.00 +/- 0.01 4.780 4.62 +/- 0.05 1.03 +/- 0.01 B4180/5 19.10 19.1 +/- 0.2 1.00 +/- 0.01 4.702 4.52 +/- 0.05 1.04 +/- 0.01 B4180/6 17.70 17.7 +/- 0.2 1.00 +/- 0.01 4.474 4.34 +/- 0.04 1.03 +/- 0.01 B4180/7 18.30 18.3 +/- 0.2 1.00 +/- 0.01 4.572 4.26 +/- 0.04 1.07 +/- 0.01 B4180/8 16.50 16.5 +/- 0.2 1.00 +/- 0.01 4.270 4.00 +/- 0.04 1.07 +/- 0.01 B4181/1 18.20 18.2 +/- 0.2 1.00 +/- 0.01 4.556 4.16 +/- 0.04 1.10 +/- 0.01 B4181/2 18.80 18.8 +/- 0.2 1.00 +/- 0.01 4.654 4.30 +/- 0.04 1.08 +/- 0.01 B4181/3 18.10 18.1 +/- 0.2 1.00 +/- 0.01 4.540 4.27 +/- 0.04 1.06 +/- 0.01 B4181/4 18.30 18.3 +/- 0.2 1.00 +/- 0.01 4.573 4.34 +/- 0.04 1.05 +/- 0.01 B3221/1 20.60 20.6 +/- 0.2 1.00 +/- 0.01 5.026 5.00 +/- 0.05 1.01 +/- 0.01 4.315 3.80 +/- 0.30 1.14 +/- 0.09 8.574 9.50 +/- 0.20 0.90 +/- 0.02 2.317 3.10 +/- 0.12 0.75 +/- 0.03 B3221/2 22.00 22.0 +/- 0.3 1.00 +/- 0.01 5.219 5.18 +/- 0.05 1.01 +/- 0.01 4.520 4.36 +/- 0.50 1.04 +/- 0.12 9.649 11.20 +/- 0.20 0.86 +/- 0.02 2.841 4.09 +/- 0.16 0.69 +/- 0.03 B3221/3 24.40 24.4 +/- 0.2 1.00 +/- 0.01 5.566 5.60 +/- 0.06 0.99 +/- 0.01 5.323 5.87 +/- 0.30 0.91 +/- 0.05 12.93 14.80 +/- 0.30 0.87 +/- 0.02 4.578 6.75 +/- 0.24 0.68 +/- 0.02 B3221/4 20.30 20.3 +/- 0.1 1.00 +/- 0.00 4.971 5.014 +/- 0.010 0.99 +/- 0.00 4.898 4.82 +/- 0.05 1.02 +/- 0.01 5.053 5.80 +/- 0.10 0.87 +/- 0.02 2.133 2.73 +/- 0.03 0.78 +/- 0.01 B3221/5 21.20 21.2 +/- 0.1 1.00 +/- 0.00 5.092 5.077 +/- 0.010 1.00 +/- 0.00 5.039 5.21 +/- 0.05 0.97 +/- 0.01 5.424 6.70 +/- 0.10 0.81 +/- 0.01 2.346 3.43 +/- 0.03 0.68 +/- 0.01 B3221/6 23.80 23.8 +/- 0.1 1.00 +/- 0.00 5.472 5.617 +/- 0.010 0.97 +/- 0.00 6.042 6.43 +/- 0.06 0.94 +/- 0.01 7.512 9.10 +/- 0.10 0.83 +/- 0.01 4.001 5.36 +/- 0.03 0.75 +/- 0.00 B4259/1 21.90 21.9 +/- 0.2 1.00 +/- 0.01 5.324 5.25 +/- 0.05 1.01 +/- 0.01 6.300 6.37 +/- 0.32 0.99 +/- 0.05 6.439 6.67 +/- 0.14 0.97 +/- 0.02 3.744 4.43 +/- 0.27 0.85 +/- 0.05 B4259/2 23.10 23.1 +/- 0.3 1.00 +/- 0.01 5.491 5.39 +/- 0.05 1.02 +/- 0.01 6.572 6.53 +/- 0.32 1.01 +/- 0.05 7.070 7.77 +/- 0.16 0.91 +/- 0.02 4.384 5.58 +/- 0.34 0.79 +/- 0.05 B4259/3 25.80 25.8 +/- 0.3 1.00 +/- 0.01 5.869 5.83 +/- 0.06 1.01 +/- 0.01 7.717 7.84 +/- 0.39 0.98 +/- 0.05 9.463 10.32 +/- 0.21 0.92 +/- 0.02 7.335 9.27 +/- 0.56 0.79 +/- 0.05 B4259/4 22.00 22.0 +/- 0.2 1.00 +/- 0.01 5.338 5.264 +/- 0.010 1.01 +/- 0.00 5.502 5.28 +/- 0.10 1.04 +/- 0.02 7.572 8.27 +/- 0.10 0.92 +/- 0.01 3.840 4.59 +/- 0.10 0.84 +/- 0.02 B4259/5 23.30 23.3 +/- 0.3 1.00 +/- 0.01 5.519 5.418 +/- 0.010 1.02 +/- 0.00 5.724 5.71 +/- 0.10 1.00 +/- 0.02 8.377 9.53 +/- 0.10 0.88 +/- 0.01 4.584 5.74 +/- 0.10 0.80 +/- 0.01 B4259/6 26.20 26.2 +/- 0.3 1.00 +/- 0.01 5.921 5.851 +/- 0.010 1.01 +/- 0.00 6.697 6.64 +/- 0.10 1.01 +/- 0.02 11.33 12.40 +/- 0.10 0.91 +/- 0.01 7.930 9.60 +/- 0.10 0.83 +/- 0.01 B3284/1 25.60 25.6 +/- 0.3 1.00 +/- 0.01 5.857 5.65 +/- 0.03 1.04 +/- 0.01 7.342 6.49 +/- 0.09 1.13 +/- 0.02 6.695 7.01 +/- 0.10 0.96 +/- 0.01 7.789 9.08 +/- 0.13 0.86 +/- 0.01 B3284/2 26.80 26.8 +/- 0.3 1.00 +/- 0.01 6.007 5.79 +/- 0.03 1.04 +/- 0.01 7.557 6.90 +/- 0.10 1.10 +/- 0.02 7.241 8.05 +/- 0.11 0.90 +/- 0.01 8.870 11.51 +/- 0.16 0.77 +/- 0.01 B3284/3 30.00 30.0 +/- 0.3 1.00 +/- 0.01 6.407 6.15 +/- 0.03 1.04 +/- 0.01 8.602 8.53 +/- 0.12 1.01 +/- 0.01 9.449 10.04 +/- 0.14 0.94 +/- 0.01 15.10 18.47 +/- 0.26 0.82 +/- 0.01 B3284/4 25.40 25.4 +/- 0.1 1.00 +/- 0.00 5.825 5.66 +/- 0.01 1.03 +/- 0.00 7.304 6.63 +/- 0.10 1.10 +/- 0.02 6.603 7.16 +/- 0.10 0.92 +/- 0.01 7.509 8.80 +/- 0.10 0.85 +/- 0.01 B3284/5 27.20 27.2 +/- 0.1 1.00 +/- 0.00 6.055 5.83 +/- 0.01 1.04 +/- 0.00 7.626 7.32 +/- 0.10 1.04 +/- 0.01 7.426 8.48 +/- 0.10 0.88 +/- 0.01 9.508 12.15 +/- 0.10 0.78 +/- 0.01 B3284/6 30.00 30.0 +/- 0.1 1.00 +/- 0.00 6.401 6.24 +/- 0.01 1.03 +/- 0.00 8.602 8.17 +/- 0.10 1.05 +/- 0.01 9.449 10.35 +/- 0.10 0.91 +/- 0.01 15.10 18.62 +/- 0.10 0.81 +/- 0.00 B3362/1 21.36 21.36 +/- 0.20 1.00 +/- 0.01 4.931 5.047 +/- 0.050 0.98 +/- 0.01 5.964 5.57 +/- 0.28 1.07 +/- 0.05 1.807 1.97 +/- 0.04 0.92 +/- 0.02 1.753 2.28 +/- 0.14 0.77 +/- 0.05 B3362/2 22.81 22.81 +/- 0.23 1.00 +/- 0.01 5.107 5.187 +/- 0.052 0.98 +/- 0.01 6.264 6.21 +/- 0.31 1.01 +/- 0.05 2.010 2.32 +/- 0.05 0.87 +/- 0.02 2.113 3.07 +/- 0.18 0.69 +/- 0.04 B3362/3 25.74 25.74 +/- 0.26 1.00 +/- 0.01 5.493 5.692 +/- 0.057 0.97 +/- 0.01 7.647 7.56 +/- 0.38 1.01 +/- 0.05 2.788 3.19 +/- 0.06 0.87 +/- 0.02 3.682 5.14 +/- 0.31 0.72 +/- 0.04 B3362/4 21.50 21.5 +/- 0.1 1.00 +/- 0.00 4.949 5.09 +/- 0.01 0.97 +/- 0.00 5.781 3.58 +/- 0.20 1.61 +/- 0.09 2.200 2.22 +/- 0.20 0.99 +/- 0.09 1.817 2.17 +/- 0.20 0.84 +/- 0.08 B3362/5 22.50 22.5 +/- 0.1 1.00 +/- 0.00 5.061 5.26 +/- 0.15 0.96 +/- 0.03 5.929 4.49 +/- 0.20 1.32 +/- 0.06 2.358 2.65 +/- 0.20 0.89 +/- 0.07 1.984 3.19 +/- 0.20 0.62 +/- 0.04 B3362/6 26.00 26.0 +/- 0.1 1.00 +/- 0.00 5.525 5.73 +/- 0.02 0.96 +/- 0.00 7.375 5.19 +/- 0.20 1.42 +/- 0.05 3.505 3.66 +/- 0.20 0.96 +/- 0.05 3.890 5.52 +/- 0.20 0.70 +/- 0.03 Mean ; SD 1.0000 ; 0.0001 1.02 ; 0.04 1.03 ; 0.15 0.93 ; 0.07 0.82 ; 0.11
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 51 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 14: AGR results for fission product activity.
Nb95/U (1E+2 Ci/t) Sb125/U (1E+3 Ci/t) Cs134/U (1E+4 Ci/t) Cs137/U (1E+4 Ci/t) Ce144/U (1E+4 Ci/t) Eu154/U (1E+3 Ci/t) Eu155/U (1E+3 Ci/t) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E B3221/1 2.297 1.220 +/- 0.049 1.88 +/- 0.08 1.303 1.13 +/- 0.01 1.15 +/- 0.01 5.280 5.33 +/- 0.03 0.99 +/- 0.01 1.671 1.75 +/- 0.33 0.96 +/- 0.18 2.179 1.258 +/- 0.054 1.73 +/- 0.07 0.5549 0.915 +/- 0.065 0.61 +/- 0.04 B3221/2 2.645 1.354 +/- 0.054 1.95 +/- 0.08 1.549 1.30 +/- 0.01 1.19 +/- 0.01 5.669 5.60 +/- 0.06 1.01 +/- 0.01 2.090 1.82 +/- 0.04 1.15 +/- 0.03 2.495 1.366 +/- 0.041 1.83 +/- 0.05 0.6141 1.041 +/- 0.064 0.59 +/- 0.04 B3221/3 3.131 1.478 +/- 0.063 2.12 +/- 0.09 1.885 1.63 +/- 0.02 1.16 +/- 0.01 6.303 6.30 +/- 0.04 1.00 +/- 0.01 2.290 1.94 +/- 0.07 1.18 +/- 0.04 3.049 1.616 +/- 0.054 1.89 +/- 0.06 0.7157 1.189 +/- 0.054 0.60 +/- 0.03 B4259/1 3.243 1.526 +/- 0.052 2.13 +/- 0.07 2.040 1.68 +/- 0.01 1.21 +/- 0.01 5.698 5.69 +/- 0.03 1.00 +/- 0.01 3.712 3.28 +/- 0.11 1.13 +/- 0.04 2.851 1.500 +/- 0.045 1.90 +/- 0.06 0.7145 1.158 +/- 0.058 0.62 +/- 0.03 B4259/2 3.510 1.659 +/- 0.074 2.12 +/- 0.09 2.230 1.92 +/- 0.01 1.16 +/- 0.01 6.018 6.07 +/- 0.03 0.99 +/- 0.00 3.886 3.48 +/- 1.00 1.12 +/- 0.32 3.134 1.626 +/- 0.049 1.93 +/- 0.06 0.7614 1.334 +/- 0.069 0.57 +/- 0.03 B4259/3 4.203 1.878 +/- 0.070 2.24 +/- 0.08 2.753 2.33 +/- 0.01 1.18 +/- 0.01 6.738 6.47 +/- 0.04 1.04 +/- 0.01 4.276 3.57 +/- 0.40 1.20 +/- 0.13 3.877 1.903 +/- 0.069 2.04 +/- 0.07 0.9019 1.345 +/- 0.067 0.67 +/- 0.03 B3284/1 4.418 2.166 +/- 0.112 2.04 +/- 0.11 3.189 2.73 +/- 0.02 1.17 +/- 0.01 6.693 7.15 +/- 0.07 0.94 +/- 0.01 5.900 5.42 +/- 0.14 1.09 +/- 0.03 4.154 2.047 +/- 0.062 2.03 +/- 0.06 0.9797 1.068 +/- 0.043 0.92 +/- 0.04 B3284/2 4.735 2.047 +/- 0.076 2.31 +/- 0.09 3.435 3.00 +/- 0.02 1.15 +/- 0.01 7.014 7.23 +/- 0.05 0.97 +/- 0.01 6.096 5.42 +/- 0.18 1.12 +/- 0.04 4.483 2.225 +/- 0.111 2.01 +/- 0.10 1.036 1.708 +/- 0.068 0.61 +/- 0.02 B3284/3 5.716 2.379 +/- 0.102 2.40 +/- 0.10 4.267 3.67 +/- 0.02 1.16 +/- 0.01 7.869 7.78 +/- 0.06 1.01 +/- 0.01 6.699 5.62 +/- 0.19 1.19 +/- 0.04 5.543 2.499 +/- 0.079 2.22 +/- 0.07 1.240 2.037 +/- 0.103 0.61 +/- 0.03 B3362/1 7.418 4.87 +/- 0.12 1.52 +/- 0.04 3.515 1.80 +/- 0.06 1.95 +/- 0.07 2.398 2.09 +/- 0.02 1.15 +/- 0.01 5.730 5.73 +/- 0.07 1.00 +/- 0.01 9.273 8.75 +/- 0.24 1.06 +/- 0.03 2.404 1.48 +/- 0.04 1.62 +/- 0.04 0.7136 1.21 +/- 0.04 0.59 +/- 0.02 B3362/2 7.791 5.18 +/- 0.17 1.50 +/- 0.05 3.858 2.17 +/- 0.07 1.78 +/- 0.06 2.671 2.40 +/- 0.02 1.11 +/- 0.01 6.127 6.10 +/- 0.07 1.00 +/- 0.01 9.834 9.13 +/- 0.25 1.08 +/- 0.03 2.709 1.63 +/- 0.05 1.66 +/- 0.05 0.7645 1.37 +/- 0.05 0.56 +/- 0.02 B3362/3 8.555 5.60 +/- 0.11 1.53 +/- 0.03 4.669 2.56 +/- 0.08 1.82 +/- 0.06 3.362 3.09 +/- 0.03 1.09 +/- 0.01 6.930 6.89 +/- 0.08 1.01 +/- 0.01 10.94 9.78 +/- 0.27 1.12 +/- 0.03 3.442 1.94 +/- 0.05 1.77 +/- 0.05 0.9094 1.58 +/- 0.05 0.58 +/- 0.02 Mean ; SD 1.52 ; 0.01 2.06 ; 0.19 1.16 ; 0.03 1.00 ; 0.03 1.12 ; 0.07 1.89 ; 0.17 0.63 ; 0.10
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 52 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 15: Irradiation history of the Obrigheim assemblies.
Cycle Start End Period length Full power Cumulative assembly (d) (d) irradiation (MWd/t) BE124 BE210 2 30/09/70 12/08/71 317 258 6600 13/08/71 29/09/71 48 0 3 30/09/71 07/09/72 344 295 9900 08/09/72 04/10/72 27 0 4 05/10/72 01/09/73 332 283 18600 21300 02/09/73 24/09/73 23 0 5 25/09/73 16/08/74 326 229 29000 30100
Table 16: Obrigheim sample characteristics and irradiations.15
Element Pin Position Height Reported Derived Derived Mean (mm) Irradiation Irradiation On-power Rating (MWd/t) (MWd/t) (MW/t) BE124 D1 P1 150 21170 21068 21.608 BE124 D1 P2 315 27910 28162 28.884 BE124 D1 P3 1435 33750 33366 34.222 BE124 E3 P1 150 20180 20067 20.582 BE124 E3 P2 315 35100 34725 35.615 BE124 E3 P3 1435 36260 35848 36.767 BE124 E3 P4 2315 30920 30630 31.415 BE124 E3 P5 2585 22860 22779 23.363 BE124 G7 P1 150 17130 17046 17.483 BE124 G7 P2 315 25830 25631 26.288 BE124 G7 P3 1435 31320 31031 31.827 BE124 G7 P4 2315 27710 27542 28.248 BE124 G7 P5 2585 25810 25631 26.288 BE124 M14 P1 150 15600 15550 15.949 BE124 M14 P3 1435 29360 29105 29.851 BE124 M14 P4 2315 24900 24733 25.367 BE210 G14 P3(1) 1328 37490 37064 36.990 BE210 G14 P4(1) 2206 35640 35208 35.138 BE210 G14 P5(1) 2426 30160 29866 29.806 BE210 G14 P5(2) 2547 24220 24074 24.026 BE210 K14 P1 150 25450 25296 25.246 BE210 K14 P3(1) 1328 36670 36242 36.170 BE210 K14 P4(1) 2206 32900 32556 32.491
15 The irradiations were derived in this work from the measured Nd148/U238 atom ratio and FISPIN (except for BE124, D1, P2, which used the Cs137/U238 atom ratio). The rating was derived from this irradiation and time on power. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 53 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 17: Obrigheim results for uranium isotopes.
Element Pin Pos U235d/Ui (kg/t) U236/Ui (kg/t) U238d/Ui (kg/t) C E C/E C E C/E C E C/E BE124 D1 P1 17.18 16.31 +/- 0.21 1.05 +/- 0.01 3.040 2.99 +/- 0.04 1.02 +/- 0.02 15.18 15.95 +/- 0.35 0.95 +/- 0.02 BE124 D1 P2 BE124 D1 P3 22.75 23.07 +/- 0.28 0.99 +/- 0.01 3.809 4.06 +/- 0.05 0.94 +/- 0.01 25.29 25.32 +/- 0.54 1.00 +/- 0.02 BE124 D1 P1 16.75 17.25 +/- 0.23 0.97 +/- 0.01 2.954 2.82 +/- 0.04 1.05 +/- 0.02 14.03 12.88 +/- 0.29 1.09 +/- 0.02 BE124 E3 P2 23.41 21.56 +/- 0.26 1.09 +/- 0.01 3.868 3.77 +/- 0.05 1.03 +/- 0.01 25.98 27.85 +/- 0.59 0.93 +/- 0.02 BE124 E3 P3 23.79 23.91 +/- 0.29 0.99 +/- 0.01 3.909 4.12 +/- 0.05 0.95 +/- 0.01 26.96 27.01 +/- 0.57 1.00 +/- 0.02 BE124 E3 P4 21.90 22.34 +/- 0.27 0.98 +/- 0.01 3.685 3.87 +/- 0.05 0.95 +/- 0.01 22.48 23.03 +/- 0.49 0.98 +/- 0.02 BE124 E3 P5 18.26 18.15 +/- 0.23 1.01 +/- 0.01 3.181 3.62 +/- 0.05 0.88 +/- 0.01 16.13 16.59 +/- 0.36 0.97 +/- 0.02 BE124 G7 P1 14.74 14.79 +/- 0.22 1.00 +/- 0.01 2.668 2.92 +/- 0.05 0.91 +/- 0.01 12.20 11.97 +/- 0.30 1.02 +/- 0.03 BE124 G7 P2 19.48 19.24 +/- 0.24 1.01 +/- 0.01 3.386 3.85 +/- 0.05 0.88 +/- 0.01 18.94 19.21 +/- 0.41 0.99 +/- 0.02 BE124 G7 P3 21.81 22.45 +/- 0.27 0.97 +/- 0.01 3.701 3.96 +/- 0.05 0.93 +/- 0.01 23.46 23.63 +/- 0.50 0.99 +/- 0.02 BE124 G7 P4 20.36 19.91 +/- 0.24 1.02 +/- 0.01 3.509 4.05 +/- 0.06 0.87 +/- 0.01 20.51 21.62 +/- 0.46 0.95 +/- 0.02 BE124 G7 P5 19.48 19.91 +/- 0.24 0.98 +/- 0.01 3.386 3.60 +/- 0.05 0.94 +/- 0.01 18.94 19.80 +/- 0.42 0.96 +/- 0.02 BE124 M14 P1 13.80 14.31 +/- 0.22 0.96 +/- 0.02 2.510 2.73 +/- 0.04 0.92 +/- 0.01 10.96 10.91 +/- 0.29 1.00 +/- 0.03 BE124 M14 P3 21.09 21.22 +/- 0.26 0.99 +/- 0.01 3.600 3.81 +/- 0.05 0.94 +/- 0.01 21.67 21.73 +/- 0.46 1.00 +/- 0.02 BE124 M14 P4 19.10 19.67 +/- 0.25 0.97 +/- 0.01 3.324 3.60 +/- 0.05 0.92 +/- 0.01 18.08 18.85 +/- 0.40 0.96 +/- 0.02 BE210 G14 P3(1) 23.12 23.57 +/- 0.29 0.98 +/- 0.01 3.762 3.88 +/- 0.05 0.97 +/- 0.01 29.08 29.08 +/- 0.62 1.00 +/- 0.02 BE210 G14 P4(1) 22.58 23.35 +/- 0.29 0.97 +/- 0.01 3.707 3.95 +/- 0.05 0.94 +/- 0.01 27.42 26.36 +/- 0.56 1.04 +/- 0.02 BE210 G14 P5(1) 20.76 22.03 +/- 0.27 0.94 +/- 0.01 3.495 3.66 +/- 0.05 0.95 +/- 0.01 22.73 20.99 +/- 0.45 1.08 +/- 0.02 BE210 G14 P5(2) 18.29 19.36 +/- 0.25 0.94 +/- 0.01 3.162 3.33 +/- 0.05 0.95 +/- 0.01 17.87 16.25 +/- 0.34 1.10 +/- 0.02 BE210 K14 P1 18.88 18.27 +/- 0.22 1.03 +/- 0.01 3.243 3.22 +/- 0.05 1.01 +/- 0.01 18.82 18.86 +/- 0.40 1.00 +/- 0.02 BE210 K14 P3(1) 22.91 23.44 +/- 0.29 0.98 +/- 0.01 3.740 3.86 +/- 0.05 0.97 +/- 0.01 28.30 27.76 +/- 0.59 1.02 +/- 0.02 BE210 K14 P4(1) 21.75 23.26 +/- 0.28 0.94 +/- 0.01 3.614 3.82 +/- 0.05 0.95 +/- 0.01 25.01 24.55 +/- 0.52 1.02 +/- 0.02 Mean ; SD 0.99 ; 0.04 0.95 ; 0.05 1.00 ; 0.04
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 54 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 18: Obrigheim results for plutonium isotopes.
Element Pin Pos Pu238/Ui (kg/t) Pu239/Ui (kg/t) Pu240/Ui (kg/t) Pu241/Ui (kg/t) Pu242/Ui (kg/t) 16 Pu/Ui (kg/t) C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E BE124 D1 P1 0.04891 0.036 +/- 0.001 1.36 +/- 0.03 4.951 4.35 +/- 0.05 1.14 +/- 0.01 1.492 1.32 +/- 0.02 1.13 +/- 0.01 0.7931 0.62 +/- 0.01 1.28 +/- 0.02 0.1671 0.128 +/- 0.00 1.31 +/- 0.02 7.452 6.45 1.15 BE124 D1 P2 BE124 D1 P3 0.1366 0.156 +/- 0.003 0.88 +/- 0.02 5.391 5.02 +/- 0.06 1.07 +/- 0.01 2.320 2.36 +/- 0.03 0.98 +/- 0.01 1.320 1.28 +/- 0.02 1.03 +/- 0.01 0.5000 0.564 +/- 0.01 0.89 +/- 0.01 9.668 9.38 1.03 BE124 D1 P1 0.04162 0.041 +/- 0.001 1.02 +/- 0.02 4.713 4.28 +/- 0.05 1.10 +/- 0.01 1.390 1.36 +/- 0.02 1.02 +/- 0.01 0.7270 0.62 +/- 0.01 1.17 +/- 0.02 0.1468 0.139 +/- 0.00 1.06 +/- 0.02 7.018 6.44 1.09 BE124 E3 P2 0.1433 0.104 +/- 0.002 1.38 +/- 0.03 5.200 4.62 +/- 0.05 1.13 +/- 0.01 2.337 1.99 +/- 0.02 1.17 +/- 0.01 1.338 1.02 +/- 0.01 1.31 +/- 0.02 0.5519 0.380 +/- 0.00 1.45 +/- 0.01 9.570 8.11 1.18 BE124 E3 P3 0.1532 0.165 +/- 0.004 0.93 +/- 0.02 5.209 4.77 +/- 0.05 1.09 +/- 0.01 2.394 2.41 +/- 0.03 0.99 +/- 0.01 1.373 1.26 +/- 0.02 1.09 +/- 0.01 0.5908 0.629 +/- 0.01 0.94 +/- 0.01 9.719 9.23 1.05 BE124 E3 P4 0.1096 0.114 +/- 0.002 0.96 +/- 0.02 5.145 4.93 +/- 0.06 1.04 +/- 0.01 2.111 2.23 +/- 0.03 0.95 +/- 0.01 1.198 1.19 +/- 0.02 1.01 +/- 0.01 0.4183 0.476 +/- 0.01 0.88 +/- 0.01 8.981 8.94 1.00 BE124 E3 P5 0.05601 0.062 +/- 0.001 0.90 +/- 0.02 4.880 4.65 +/- 0.05 1.05 +/- 0.01 1.592 1.62 +/- 0.02 0.98 +/- 0.01 0.8606 0.84 +/- 0.01 1.02 +/- 0.01 0.2041 0.211 +/- 0.00 0.97 +/- 0.01 7.593 7.38 1.03 BE124 G7 P1 0.03037 0.031 +/- 0.001 0.98 +/- 0.02 4.660 4.26 +/- 0.05 1.09 +/- 0.01 1.175 1.16 +/- 0.01 1.01 +/- 0.01 0.5913 0.55 +/- 0.01 1.08 +/- 0.01 0.09536 0.099 +/- 0.00 0.96 +/- 0.02 6.553 6.10 1.07 BE124 G7 P2 0.07809 0.079 +/- 0.002 0.99 +/- 0.02 5.259 4.70 +/- 0.05 1.12 +/- 0.01 1.833 1.81 +/- 0.02 1.01 +/- 0.01 1.020 0.94 +/- 0.01 1.09 +/- 0.01 0.2728 0.279 +/- 0.00 0.98 +/- 0.01 8.464 7.81 1.08 BE124 G7 P3 0.1190 0.141 +/- 0.003 0.84 +/- 0.02 5.422 5.02 +/- 0.06 1.08 +/- 0.01 2.190 2.28 +/- 0.03 0.96 +/- 0.01 1.246 1.20 +/- 0.02 1.04 +/- 0.01 0.4252 0.489 +/- 0.01 0.87 +/- 0.01 9.401 9.13 1.03 BE124 G7 P4 0.09169 0.106 +/- 0.002 0.86 +/- 0.02 5.330 5.08 +/- 0.06 1.05 +/- 0.01 1.965 2.04 +/- 0.02 0.96 +/- 0.01 1.105 1.11 +/- 0.01 1.00 +/- 0.01 0.3236 0.366 +/- 0.00 0.88 +/- 0.01 8.815 8.70 1.01 BE124 G7 P5 0.07809 0.079 +/- 0.002 0.99 +/- 0.02 5.259 5.08 +/- 0.06 1.04 +/- 0.01 1.833 1.95 +/- 0.02 0.94 +/- 0.01 1.020 1.05 +/- 0.01 0.97 +/- 0.01 0.2728 0.320 +/- 0.00 0.85 +/- 0.01 8.464 8.48 1.00 BE124 M14 P1 0.02391 0.026 +/- 0.001 0.92 +/- 0.02 4.443 3.98 +/- 0.04 1.12 +/- 0.01 1.050 1.04 +/- 0.01 1.01 +/- 0.01 0.5068 0.46 +/- 0.01 1.10 +/- 0.02 0.07353 0.075 +/- 0.00 0.98 +/- 0.02 6.097 5.58 1.09 BE124 M14 P3 0.1018 0.107 +/- 0.002 0.95 +/- 0.02 5.312 5.02 +/- 0.06 1.06 +/- 0.01 2.062 2.08 +/- 0.03 0.99 +/- 0.01 1.161 1.12 +/- 0.01 1.04 +/- 0.01 0.3684 0.384 +/- 0.00 0.96 +/- 0.01 9.005 8.71 1.03 BE124 M14 P4 0.07077 0.076 +/- 0.002 0.93 +/- 0.02 5.159 4.96 +/- 0.06 1.04 +/- 0.01 1.765 1.86 +/- 0.02 0.95 +/- 0.01 0.9710 1.00 +/- 0.01 0.97 +/- 0.01 0.2502 0.299 +/- 0.00 0.84 +/- 0.01 8.215 8.20 1.00 BE210 G14 P3(1) 0.1697 0.165 +/- 0.004 1.03 +/- 0.02 5.271 4.56 +/- 0.05 1.16 +/- 0.01 2.547 2.49 +/- 0.03 1.02 +/- 0.01 1.421 1.31 +/- 0.02 1.08 +/- 0.01 0.6636 0.780 +/- 0.01 0.85 +/- 0.01 10.07 9.31 1.08 BE210 G14 P4(1) 0.1531 0.159 +/- 0.003 0.96 +/- 0.02 5.260 4.41 +/- 0.05 1.19 +/- 0.01 2.455 2.38 +/- 0.03 1.03 +/- 0.01 1.368 1.21 +/- 0.02 1.13 +/- 0.01 0.5976 0.680 +/- 0.01 0.88 +/- 0.01 9.834 8.84 1.11 BE210 G14 P5(1) 0.1086 0.114 +/- 0.002 0.95 +/- 0.02 5.191 4.36 +/- 0.05 1.19 +/- 0.01 2.153 2.11 +/- 0.03 1.02 +/- 0.01 1.188 1.09 +/- 0.01 1.09 +/- 0.01 0.4193 0.494 +/- 0.01 0.85 +/- 0.01 9.060 8.17 1.11 BE210 G14 P5(2) 0.06749 0.065 +/- 0.001 1.04 +/- 0.02 5.015 4.27 +/- 0.05 1.17 +/- 0.01 1.763 1.72 +/- 0.02 1.03 +/- 0.01 0.9463 0.86 +/- 0.01 1.10 +/- 0.01 0.2531 0.285 +/- 0.00 0.89 +/- 0.01 8.045 7.20 1.12 BE210 K14 P1 0.07517 0.065 +/- 0.001 1.16 +/- 0.02 5.046 4.60 +/- 0.05 1.10 +/- 0.01 1.850 1.74 +/- 0.02 1.06 +/- 0.01 0.9989 0.90 +/- 0.01 1.11 +/- 0.01 0.2855 0.264 +/- 0.00 1.08 +/- 0.01 8.255 7.57 1.09 BE210 K14 P3(1) 0.1619 0.169 +/- 0.004 0.96 +/- 0.02 5.247 4.69 +/- 0.05 1.12 +/- 0.01 2.505 2.47 +/- 0.03 1.01 +/- 0.01 1.395 1.30 +/- 0.02 1.07 +/- 0.01 0.6351 0.735 +/- 0.01 0.86 +/- 0.01 9.944 9.36 1.06 BE210 K14 P4(1) 0.1300 0.126 +/- 0.003 1.03 +/- 0.02 5.214 4.51 +/- 0.05 1.16 +/- 0.01 2.310 2.37 +/- 0.03 0.97 +/- 0.01 1.281 1.21 +/- 0.02 1.06 +/- 0.01 0.5073 0.658 +/- 0.01 0.77 +/- 0.01 9.443 8.87 1.06 Mean ; SD 1.00 ; 0.14 1.10 ; 0.05 1.01 ; 0.06 1.08 ; 0.09 0.95 ; 0.16 1.07 ; 0.05
16 Derived in this work by summing isotopic results. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 55 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 19: Obrigheim results for minor actinides.
Element Pin Pos Am241/Ui (1E-2 kg/t) Am242M/Ui (1E-4 kg/t) Am243/Ui (1E-2 kg/t) Cm242/Ui (1E-3 kg/t) Cm244/Ui (1E-3 kg/t) Set A Set B17 Ispra Karlsruhe18 Ispra Karlsruhe C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E C E C/E BE124 D1 P1 2.446 2.19 1.12 5.061 7.40 0.68 3.174 2.22 1.43 BE124 D1 P2 BE124 D1 P3 3.486 6.08 0.57 13.66 15.65 +/- 0.67 0.87 +/- 0.04 28.27 33.97 +/- 0.24 0.83 +/- 0.01 BE124 D1 P1 2.243 2.93 0.77 4.392 4.50 +/- 0.19 0.98 +/- 0.04 2.310 2.04 +/- 0.09 1.13 +/- 0.05 BE124 E3 P2 32.67 12.58 2.60 BE124 E3 P3 3.437 9.00 0.38 15.37 14.79 +/- 0.63 1.04 +/- 0.04 37.79 41.62 +/- 0.29 0.91 +/- 0.01 BE124 E3 P4 3.253 7.30 0.45 11.47 15.01 +/- 0.64 0.76 +/- 0.03 11.47 33.17 0.35 18.26 24.80 +/- 0.24 0.74 +/- 0.01 18.26 22.18 0.82 BE124 E3 P5 2.585 2.27 1.14 5.991 7.10 +/- 0.30 0.84 +/- 0.04 4.353 5.13 +/- 0.18 0.85 +/- 0.03 BE124 G7 P1 1.888 1.40 +/- 0.27 1.35 +/- 0.26 2.205 2.88 0.77 0.8568 0.86 1.00 2.980 2.94 +/- 0.12 1.01 +/- 0.04 1.134 1.04 +/- 0.06 1.09 +/- 0.06 BE124 G7 P2 3.007 2.48 +/- 0.50 1.21 +/- 0.24 3.842 4.94 0.78 3.867 3.90 0.99 8.041 8.58 +/- 0.37 0.94 +/- 0.04 8.446 9.49 +/- 0.24 0.89 +/- 0.02 BE124 G7 P3 3.422 17.58 0.19 11.97 14.79 +/- 0.63 0.81 +/- 0.03 11.97 27.15 0.44 20.65 29.73 +/- 0.26 0.69 +/- 0.01 20.65 26.73 0.77 BE124 G7 P4 3.179 13.98 0.23 9.391 11.88 +/- 0.51 0.79 +/- 0.03 11.87 16.52 +/- 0.31 0.72 +/- 0.01 BE124 G7 P5 8.041 19.56 0.41 8.446 10.68 0.79 BE124 M14 P1 1.629 0.67 2.43 0.6847 1.04 0.66 BE124 M14 P3 3.260 9.39 0.35 10.47 11.30 +/- 0.48 0.93 +/- 0.04 15.05 17.99 +/- 0.25 0.84 +/- 0.01 BE124 M14 P4 7.376 14.07 0.52 6.946 8.91 0.78 BE210 G14 P3(1) 4.102 4.10 +/- 0.86 1.00 +/- 0.21 5.264 7.29 0.72 14.00 15.4 0.91 16.48 15.54 +/- 0.67 1.06 +/- 0.05 16.48 47.03 0.35 49.39 59.81 +/- 0.42 0.83 +/- 0.01 49.39 45.94 1.08 BE210 G14 P4(1) 4.067 4.03 +/- 0.84 1.01 +/- 0.21 5.200 19.30 0.27 11.95 13.8 0.87 15.14 14.36 +/- 0.62 1.05 +/- 0.05 39.36 47.15 +/- 0.33 0.83 +/- 0.01 BE210 G14 P5(1) 3.821 5.53 0.69 4.811 12.07 0.40 7.028 4.20 1.67 11.23 11.70 +/- 0.50 0.96 +/- 0.04 18.66 22.07 +/- 0.26 0.85 +/- 0.01 BE210 G14 P5(2) 3.273 2.77 +/- 0.55 1.18 +/- 0.24 3.993 7.10 0.56 3.344 3.62 0.92 7.159 7.56 +/- 0.32 0.95 +/- 0.04 6.741 6.95 +/- 0.21 0.97 +/- 0.03 BE210 K14 P1 3.403 2.52 +/- 0.51 1.35 +/- 0.27 7.975 8.13 +/- 0.35 0.98 +/- 0.04 8.534 6.53 +/- 0.17 1.31 +/- 0.03 BE210 K14 P3(1) 4.071 7.49 0.54 5.210 7.57 0.69 13.09 14.00 0.93 15.88 17.75 +/- 0.76 0.89 +/- 0.04 44.80 52.59 +/- 0.37 0.85 +/- 0.01 BE210 K14 P4(1) 13.20 33.10 0.40 27.70 31.68 0.87 Mean ; SD 1.33 ; 0.46 0.53 ; 0.28 0.60 ; 0.20 1.04 ; 0.28 0.93 ; 0.09 0.45 ; 0.12 0.90 ; 0.16 1.09 ; 0.61
17 It is suggested in reference 21 that Set B may be unreliable. 18 It is suggested in reference 21 that the Karlsruhe results for Cm242/U238 may be biased. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 56 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 20: Obrigheim results for Nd148, Cs134, Cs137 and Eu154.
Element Pin Pos Nd148/U238 (1E-4 a/a) Cs134/U (1E+9 Bq/g) Cs137/U (1E+9 Bq/g) Eu154/U (1E+8 Bq/g) C E C/E C E C/E C E C/E C E C/E BE124 D1 P1 4.010 4.01 +/- 0.04 1.00 +/- 0.01 BE124 D1 P2 4.921 4.287 +/- 0.064 1.15 +/- 0.02 3.436 3.308 +/- 0.050 1.04 +/- 0.02 2.678 1.916 +/- 0.096 1.40 +/- 0.07 BE124 D1 P3 6.458 6.46 +/- 0.06 1.00 +/- 0.01 6.922 6.512 +/- 0.098 1.06 +/- 0.02 4.094 4.097 +/- 0.061 1.00 +/- 0.01 3.801 2.652 +/- 0.133 1.43 +/- 0.07 BE124 D1 P1 3.811 3.81 +/- 0.04 1.00 +/- 0.01 2.421 2.115 +/- 0.032 1.14 +/- 0.02 2.426 2.372 +/- 0.036 1.02 +/- 0.02 1.242 0.779 +/- 0.039 1.59 +/- 0.08 BE124 E3 P2 6.728 6.73 +/- 0.07 1.00 +/- 0.01 BE124 E3 P3 6.958 6.96 +/- 0.07 1.00 +/- 0.01 7.879 6.926 +/- 0.104 1.14 +/- 0.02 4.409 4.361 +/- 0.065 1.01 +/- 0.02 4.310 2.555 +/- 0.128 1.69 +/- 0.08 BE124 E3 P4 5.899 5.90 +/- 0.06 1.00 +/- 0.01 5.733 5.468 +/- 0.082 1.05 +/- 0.02 3.747 3.774 +/- 0.057 0.99 +/- 0.01 3.132 2.147 +/- 0.107 1.46 +/- 0.07 BE124 E3 P5 4.341 4.34 +/- 0.04 1.00 +/- 0.01 3.135 3.084 +/- 0.046 1.02 +/- 0.02 2.762 2.751 +/- 0.041 1.00 +/- 0.02 1.650 1.186 +/- 0.059 1.39 +/- 0.07 BE124 G7 P1 3.230 3.23 +/- 0.03 1.00 +/- 0.01 1.802 1.714 +/- 0.026 1.05 +/- 0.02 2.053 2.053 +/- 0.031 1.00 +/- 0.02 0.8944 0.547 +/- 0.027 1.64 +/- 0.08 BE124 G7 P2 4.910 4.91 +/- 0.05 1.00 +/- 0.01 4.111 3.749 +/- 0.056 1.10 +/- 0.02 3.118 3.041 +/- 0.046 1.03 +/- 0.02 2.213 1.653 +/- 0.083 1.34 +/- 0.07 BE124 G7 P3 5.989 5.99 +/- 0.06 1.00 +/- 0.01 6.040 5.940 +/- 0.089 1.02 +/- 0.02 3.798 3.871 +/- 0.058 0.98 +/- 0.01 3.310 2.481 +/- 0.124 1.33 +/- 0.07 BE124 G7 P4 5.290 5.29 +/- 0.05 1.00 +/- 0.01 4.753 4.752 +/- 0.071 1.00 +/- 0.02 3.358 3.356 +/- 0.050 1.00 +/- 0.02 2.580 1.999 +/- 0.100 1.29 +/- 0.06 BE124 G7 P5 4.910 4.91 +/- 0.05 1.00 +/- 0.01 BE124 M14 P1 2.940 2.94 +/- 0.03 1.00 +/- 0.01 BE124 M14 P3 5.600 5.60 +/- 0.06 1.00 +/- 0.01 5.259 5.068 +/- 0.076 1.04 +/- 0.02 3.554 3.539 +/- 0.053 1.00 +/- 0.02 2.870 2.102 +/- 0.105 1.37 +/- 0.07 BE124 M14 P4 4.730 4.73 +/- 0.05 1.00 +/- 0.01 BE210 G14 P3(1) 7.197 7.20 +/- 0.07 1.00 +/- 0.01 8.322 7.597 +/- 0.114 1.10 +/- 0.02 4.571 4.665 +/- 0.070 0.98 +/- 0.01 4.741 2.743 +/- 0.137 1.73 +/- 0.09 BE210 G14 P4(1) 6.818 6.82 +/- 0.07 1.00 +/- 0.01 7.514 6.842 +/- 0.103 1.10 +/- 0.02 4.334 4.376 +/- 0.066 0.99 +/- 0.01 4.292 2.609 +/- 0.130 1.65 +/- 0.08 BE210 G14 P5(1) 5.740 5.74 +/- 0.06 1.00 +/- 0.01 5.406 5.091 +/- 0.076 1.06 +/- 0.02 3.655 3.758 +/- 0.056 0.97 +/- 0.01 3.079 2.079 +/- 0.104 1.48 +/- 0.07 BE210 G14 P5(2) 4.591 4.59 +/- 0.05 1.00 +/- 0.01 3.500 3.244 +/- 0.049 1.08 +/- 0.02 2.927 2.968 +/- 0.045 0.99 +/- 0.01 1.944 1.338 +/- 0.067 1.45 +/- 0.07 BE210 K14 P1 4.831 4.83 +/- 0.05 1.00 +/- 0.01 3.864 3.236 +/- 0.049 1.19 +/- 0.02 3.080 2.782 +/- 0.042 1.11 +/- 0.02 2.162 1.364 +/- 0.068 1.58 +/- 0.08 BE210 K14 P3(1) 7.028 7.03 +/- 0.07 1.00 +/- 0.01 7.956 7.353 +/- 0.110 1.08 +/- 0.02 4.466 4.438 +/- 0.067 1.01 +/- 0.02 4.537 2.909 +/- 0.145 1.56 +/- 0.08 BE210 K14 P4(1) 6.279 6.28 +/- 0.06 1.00 +/- 0.01 Mean ; SD 0.9999 ; 0.0002 1.08 ; 0.05 1.01 ; 0.03 1.49 ; 0.14
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Table 21: Obrigheim results for krypton isotopes with respect to Kr86 and xenon isotopes with respect to Xe134.
Element Pin Pos Kr83/86 (a/a) Kr84/86 (a/a) Xe130/Xe134 (a/a) Xe131/Xe134 (a/a) Xe132/Xe134 (a/a) Xe136/Xe134 (a/a) C E C/E C E C/E C E C/E C E C C E C/E BE124 D1 P1 0.2510 0.134 +/- 0.000 1.87 +/- 0.01 0.5657 0.305 +/- 0.001 1.85 +/- 0.00 0.002962 0.002 +/- 0.000 1.23 +/- 0.01 0.3349 0.335 +/- 0.001 1.00 +/- 0.00 0.6814 0.685 +/- 0.001 0.99 +/- 0.00 1.414 1.412 +/- 0.003 1.00 +/- 0.00 BE124 D1 P2 BE124 D1 P3 BE124 D1 P1 BE124 E3 P2 0.2248 0.233 +/- 0.001 0.97 +/- 0.00 0.6032 0.613 +/- 0.001 0.98 +/- 0.00 0.005623 0.005 +/- 0.000 1.22 +/- 0.01 0.2931 0.306 +/- 0.001 0.96 +/- 0.00 0.7436 0.734 +/- 0.001 1.01 +/- 0.00 1.534 1.520 +/- 0.003 1.01 +/- 0.00 BE124 E3 P3 BE124 E3 P4 0.2328 0.231 +/- 0.001 1.01 +/- 0.00 0.5918 0.611 +/- 0.001 0.97 +/- 0.00 0.004768 0.005 +/- 0.000 0.97 +/- 0.00 0.3063 0.296 +/- 0.001 1.03 +/- 0.00 0.7247 0.625 +/- 0.001 1.16 +/- 0.00 1.506 1.518 +/- 0.003 0.99 +/- 0.00 BE124 E3 P5 BE124 G7 P1 0.2578 0.255 +/- 0.001 1.01 +/- 0.00 0.5554 0.573 +/- 0.001 0.97 +/- 0.00 0.002306 0.002 +/- 0.000 0.96 +/- 0.00 0.3463 0.333 +/- 0.001 1.04 +/- 0.00 0.6622 0.656 +/- 0.001 1.01 +/- 0.00 1.361 1.400 +/- 0.003 0.97 +/- 0.00 BE124 G7 P2 BE124 G7 P3 0.2336 0.229 +/- 0.001 1.02 +/- 0.00 0.5919 0.613 +/- 0.001 0.97 +/- 0.00 0.004772 0.005 +/- 0.000 0.97 +/- 0.00 0.3027 0.294 +/- 0.001 1.03 +/- 0.00 0.7309 0.757 +/- 0.002 0.97 +/- 0.00 1.503 1.534 +/- 0.003 0.98 +/- 0.00 BE124 G7 P4 BE124 G7 P5 0.2434 0.245 +/- 0.001 0.99 +/- 0.00 0.5775 0.602 +/- 0.001 0.96 +/- 0.00 0.003751 0.004 +/- 0.000 1.04 +/- 0.01 0.3200 0.304 +/- 0.001 1.05 +/- 0.00 0.7052 0.723 +/- 0.001 0.98 +/- 0.00 1.459 1.487 +/- 0.003 0.98 +/- 0.00 BE124 M14 P1 0.2600 0.257 +/- 0.001 1.01 +/- 0.00 0.5516 0.567 +/- 0.001 0.97 +/- 0.00 0.002078 0.002 +/- 0.000 1.04 +/- 0.01 0.3512 0.339 +/- 0.001 1.04 +/- 0.00 0.6534 0.649 +/- 0.001 1.01 +/- 0.00 1.340 1.375 +/- 0.003 0.97 +/- 0.00 BE124 M14 P3 BE124 M14 P4 0.2447 0.241 +/- 0.001 1.02 +/- 0.00 0.5753 0.594 +/- 0.001 0.97 +/- 0.00 0.003599 0.004 +/- 0.000 1.00 +/- 0.00 0.3235 0.303 +/- 0.001 1.07 +/- 0.00 0.6995 0.700 +/- 0.001 1.00 +/- 0.00 1.452 1.491 +/- 0.003 0.97 +/- 0.00 BE210 G14 P3(1) 0.2189 0.212 +/- 0.001 1.03 +/- 0.00 0.6136 0.631 +/- 0.001 0.97 +/- 0.00 0.006411 0.007 +/- 0.000 0.99 +/- 0.00 0.2840 0.275 +/- 0.001 1.03 +/- 0.00 0.7618 0.761 +/- 0.002 1.00 +/- 0.00 1.553 1.585 +/- 0.003 0.98 +/- 0.00 BE210 G14 P4(1) BE210 G14 P5(1) BE210 G14 P5(2) BE210 K14 P1 BE210 K14 P3(1) BE210 K14 P4(1) 0.2277 0.241 +/- 0.001 0.94 +/- 0.00 0.6009 0.594 +/- 0.001 1.01 +/- 0.00 0.005417 0.004 +/- 0.000 1.50 +/- 0.01 0.2987 0.303 +/- 0.001 0.99 +/- 0.00 0.7409 0.700 +/- 0.001 1.06 +/- 0.00 1.525 1.491 +/- 0.003 1.02 +/- 0.00 Mean ; SD 1.09 ; 0.28 1.06 ; 0.28 1.09 ; 0.18 1.02 ; 0.03 1.02 ; 0.06 0.99 ; 0.02
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Table 22: Irradiation history of the Calvert Cliffs Unit 1 reactor.
Cycle Start Stop Duration of Duration of Average boron Cycle following concentration (d) shutdown (µg/g) (d) 1 07/10/74 31/12/76 816 81 330.8 2 22/03/77 22/01/78 306 71 330.8 3 03/04/78 20/04/79 382 81 469.4 4 10/07/79 18/10/80 466 85 503.7 5 11/01/81 17/04/82 461 492.1
Table 23: The rods from Calvert Cliffs analysed as part of the ATM programme.
ATM Number Cycles Assembly Rod analysed Enrichment Time to % analysis (d) ATM-103 2-4 D101 MLA098 2.72 2374 ATM-104 2-5 D047 MKP109 3.038 1870 ATM-106 1-4 BT03 NBD107 2.453 2447
Table 24: Simplified irradiation histories representative of those of the ATM samples.19
Cycle ATM-103 ATM-104 ATM-106 Duration Power Duration Power Duration Power (d) (MW/t) (d) (MW/t) (d) (MW/t) 1 465.0 29.66 1 33.0 0.00 1 168.7 28.33 1 63.3 17.28 down 81.0 0.00 2 306.0 32.09 306.0 32.87 306.0 25.18 down 71.0 0.00 71.0 0.00 71.0 0.00 3 21.9 25.21 21.9 30.76 25.0 16.72 3 19.5 17.59 19.4 20.41 25.3 8.93 3 228.4 28.51 227.7 38.14 218.7 19.32 3 25.0 0.00 25.0 0.00 25.0 0.00 3 88.0 28.51 88.0 31.14 88.0 20.98 down 81.0 0.00 81.0 0.00 81.0 0.00 4 119.1 24.56 118.3 27.27 116.7 19.44 4 121.8 12.13 121.8 13.43 123.9 9.33 4 225.1 25.25 225.9 27.25 225.4 21.34 down 85.0 0.00 5 461.0 21.43
19 Based upon rods MLA098, MKP104 and NBD107 for ATM-103, ATM-104 and ATM-106, respectively. (These rods were considered by the MCC to be representative of all the rods from their host assemblies.) IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 59 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 25: Identification, height, irradiation, and mean on power rating for the ATM samples.20
Sample ID Height Irradiation Mean on-power (mm) (GWd/t) rating (MW/t) 103-MLA098-E 328.0 24.83 21.98 103-MLA098-J 249.4 33.44 29.60 103-MLA098-P 166.7 33.17 29.36 103-MLA098-S 161.9 33.01 29.22 103-MLA098-T 160.0 33.01 29.22 103-MLA098-BB 29.3 26.62 23.56 103-MLA098-DD 25.7 25.49 22.56 103-MLA098-EE 23.6 24.61 21.78 103-MLA098-JJ 13.9 18.68 16.53 103-MLA098-LL 10.2 15.58 13.79 103-MLA098-MM 8.2 12.92 11.44 104-MKP109-E 327.9 33.4 21.01 104-MKP109-J 249.2 44.3 27.86 104-MKP109-P 166.4 44.34 27.89 104-MKP109-T 161.7 44.4 27.92 104-MKP109-U 159.7 44.4 27.92 104-MKP109-CC 29.7 37.12 23.35 104-MKP109-FF 26.3 34.9 21.95 104-MKP109-GG 24.3 33.8 21.26 104-MKP109-LL 15.0 27.35 17.20 104-MKP109-OO 11.6 22.7 14.28 104-MKP109-PP 9.6 20.4 12.83 106-NBD107-E 332.7 28.89 15.82 106-NBD107-I 284.5 46.36 25.39 106-NBD107-Q 166.0 46.46 25.44 106-NBD107-U 161.4 46.51 25.47 106-NBD107-V 159.4 46.83 25.65 106-NBD107-BB 138.4 47.05 25.77 106-NBD107-CC 136.5 46.63 25.54 106-NBD107-GG 24.7 37.27 20.41 106-NBD107-MM 16.1 31.40 17.20 106-NBD107-PP 12.7 29.49 16.15 106-NBD107-QQ 10.7 26.75 14.65
20 Mean on-power rating derived in this work from reported irradiation and on-power days. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 60 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 26: Calvert Cliffs results for the uranium isotopes.
Sample ID U234/fuel (g/g) U235/fuel (g/g) U236/fuel (g/g) U238/fuel (g/g) CEC/ECE C/ECEC/ECE C/E 103-MLA098-P 1.228E-4 (1.2 +/- 0.02)E-4 1.02 +/- 0.02 5.140E-3 (4.78 +/- 0.08)E-3 1.08 +/- 0.02 3.112E-3 (3.26 +/- 0.05)E-3 0.95 +/- 0.02 8.341E-1 (8.422 +/- 0.135)E-1 0.99 +/- 0.02 103-MLA098-BB 1.361E-4 (1.21 +/- 0.02)E-4 1.13 +/- 0.02 7.220E-3 (6.94 +/- 0.11)E-3 1.04 +/- 0.02 2.856E-3 (2.99 +/- 0.05)E-3 0.96 +/- 0.02 8.391E-1 (8.538 +/- 0.137)E-1 0.98 +/- 0.02 103-MLA098-JJ 1.547E-4 (1.4 +/- 0.02)E-4 1.10 +/- 0.02 1.060E-2 (1.025 +/- 0.016)E-2 1.03 +/- 0.02 2.369E-3 (2.50 +/- 0.04)E-3 0.95 +/- 0.02 8.449E-1 (8.551 +/- 0.137)E-1 0.99 +/- 0.02 104-MKP109-P 1.200E-4 (1.2 +/- 0.02)E-4 1.00 +/- 0.02 3.631E-3 (3.54 +/- 0.06)E-3 1.03 +/- 0.02 3.684E-3 (3.69 +/- 0.06)E-3 1.00 +/- 0.02 8.238E-1 (8.249 +/- 0.132)E-1 1.00 +/- 0.02 104-MKP109-CC 1.341E-4 (1.4 +/- 0.02)E-4 0.96 +/- 0.02 5.353E-3 (5.17 +/- 0.08)E-3 1.04 +/- 0.02 3.529E-3 (3.53 +/- 0.06)E-3 1.00 +/- 0.02 8.295E-1 (8.327 +/- 0.133)E-1 1.00 +/- 0.02 104-MKP109-LL 1.562E-4 (1.6 +/- 0.03)E-4 0.98 +/- 0.02 8.661E-3 (8.47 +/- 0.14)E-3 1.02 +/- 0.02 3.118E-3 (3.14 +/- 0.05)E-3 0.99 +/- 0.02 8.368E-1 (8.425 +/- 0.135)E-1 0.99 +/- 0.02 106-NBD107-Q 8.983E-5 (7.49 +/- 0.12)E-5 1.20 +/- 0.02 1.557E-3 (1.406 +/- 0.022)E-3 1.11 +/- 0.02 3.000E-3 (3.04 +/- 0.05)E-3 0.99 +/- 0.02 8.249E-1 (8.272 +/- 0.132)E-1 1.00 +/- 0.02 106-NBD107-GG 1.023E-4 (1.27 +/- 0.02)E-4 0.81 +/- 0.01 2.864E-3 (2.71 +/- 0.04)E-3 1.06 +/- 0.02 2.953E-3 (3.03 +/- 0.05)E-3 0.97 +/- 0.02 8.329E-1 (8.438 +/- 0.135)E-1 0.99 +/- 0.02 106-NBD107-MM 1.116E-4 (1.53 +/- 0.02)E-4 0.73 +/- 0.01 4.143E-3 (3.86 +/- 0.06)E-3 1.07 +/- 0.02 2.836E-3 (2.86 +/- 0.05)E-3 0.99 +/- 0.02 8.377E-1 (8.446 +/- 0.135)E-1 0.99 +/- 0.02 Mean ; SD 0.99 ; 0.15 1.05 ; 0.03 0.98 ; 0.02 0.99 ; 0.01
Table 27: Calvert Cliffs results for the plutonium isotopes.
Sample ID Pu238/fuel (g/g) Pu239/fuel (g/g) Pu240/fuel (g/g) Pu241/fuel (g/g) Pu242/fuel (g/g) C E C/E C E C/E C E C/E C E C/E C E C/E 103-MLA098-P 1.356E-4 (1.483 +/- 0.024)E-4 0.91 +/- 0.01 4.669E-3 (4.187 +/- 0.067)E-3 1.12 +/- 0.02 2.130E-3 (2.111 +/- 0.034)E-3 1.01 +/- 0.02 8.378E-4 (8.125 +/- 0.130)E-4 1.03 +/- 0.02 4.801E-4 (5.474 +/- 0.088)E-4 0.88 +/- 0.01 103-MLA098-BB 8.593E-5 (9.69 +/- 0.16)E-5 0.89 +/- 0.01 4.553E-3 (4.252 +/- 0.068)E-3 1.07 +/- 0.02 1.766E-3 (1.766 +/- 0.028)E-3 1.00 +/- 0.02 6.835E-4 (6.822 +/- 0.109)E-4 1.00 +/- 0.02 2.953E-4 (3.301 +/- 0.053)E-4 0.89 +/- 0.01 103-MLA098-JJ 3.866E-5 (4.85 +/- 0.08)E-5 0.80 +/- 0.01 4.187E-3 (3.954 +/- 0.063)E-3 1.06 +/- 0.02 1.228E-3 (1.243 +/- 0.020)E-3 0.99 +/- 0.02 4.448E-4 (4.543 +/- 0.073)E-4 0.98 +/- 0.02 1.230E-4 (1.394 +/- 0.022)E-4 0.88 +/- 0.01 104-MKP109-P 2.492E-4 (2.688 +/- 0.043)E-4 0.93 +/- 0.01 4.724E-3 (4.357 +/- 0.070)E-3 1.08 +/- 0.02 2.518E-3 (2.543 +/- 0.041)E-3 0.99 +/- 0.02 1.046E-3 (1.020 +/- 0.016)E-3 1.03 +/- 0.02 7.551E-4 (8.401 +/- 0.134)E-4 0.90 +/- 0.01 104-MKP109-CC 1.794E-4 (1.893 +/- 0.030)E-4 0.95 +/- 0.02 4.719E-3 (4.357 +/- 0.070)E-3 1.08 +/- 0.02 2.228E-3 (2.239 +/- 0.036)E-3 1.00 +/- 0.02 9.297E-4 (9.028 +/- 0.144)E-4 1.03 +/- 0.02 5.310E-4 (5.761 +/- 0.092)E-4 0.92 +/- 0.01 104-MKP109-LL 9.497E-4 (1.012 +/- 0.016)E-4 0.94 +/- 0.02 4.587E-3 (4.264 +/- 0.068)E-3 1.08 +/- 0.02 1.709E-3 (1.719 +/- 0.028)E-3 0.99 +/- 0.02 7.004E-4 (6.812 +/- 0.109)E-4 1.03 +/- 0.02 2.680E-4 (2.886 +/- 0.046)E-4 0.93 +/- 0.01 106-NBD107-Q 2.653E-4 (2.842 +/- 0.045)E-4 0.93 +/- 0.01 4.226E-3 (3.766 +/- 0.060)E-3 1.12 +/- 0.02 2.583E-3 (2.599 +/- 0.042)E-3 0.99 +/- 0.02 9.442E-4 (8.862 +/- 0.142)E-4 1.07 +/- 0.02 1.001E-3 (1.169 +/- 0.019)E-3 0.86 +/- 0.01 106-NBD107-GG 1.876E-4 (1.947 +/- 0.031)E-4 0.96 +/- 0.02 4.206E-3 (3.835 +/- 0.061)E-3 1.10 +/- 0.02 2.301E-3 (2.321 +/- 0.037)E-3 0.99 +/- 0.02 8.428E-4 (8.130 +/- 0.130)E-4 1.04 +/- 0.02 6.807E-4 (7.753 +/- 0.124)E-4 0.88 +/- 0.01 106-NBD107-MM 1.369E-4 (1.426 +/- 0.023)E-4 0.96 +/- 0.02 4.172E-3 (3.814 +/- 0.061)E-3 1.09 +/- 0.02 2.050E-3 (2.067 +/- 0.033)E-3 0.99 +/- 0.02 7.457E-4 (7.260 +/- 0.116)E-4 1.03 +/- 0.02 4.824E-4 (5.463 +/- 0.087)E-4 0.88 +/- 0.01 Mean ; SD 0.92 ; 0.05 1.09 ; 0.02 0.99 ; 0.01 1.02 ; 0.02 0.89 ; 0.02
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Table 28: Calvert Cliffs results for plutonium.21
Sample ID Pu/fuel (g/g) CEC/E 103-MLA098-P 8.252E-3 7.806E-3 1.06 103-MLA098-BB 7.383E-3 7.127E-3 1.04 103-MLA098-JJ 6.021E-3 5.839E-3 1.03 104-MKP109-P 9.292E-3 9.029E-3 1.03 104-MKP109-CC 8.587E-3 8.264E-3 1.04 104-MKP109-LL 7.359E-3 7.054E-3 1.04 106-NBD107-Q 9.020E-3 8.704E-3 1.04 106-NBD107-GG 8.218E-3 7.939E-3 1.04 106-NBD107-MM 7.587E-3 7.296E-3 1.04 Mean ; SD 1.04 ; 0.01
Table 29: Calvert Cliffs results for the minor actinides.
Sample ID Np237/fuel (Ci/g) Am241/fuel (Ci/g) Cm243+Cm244/fuel (Ci/g) C E C/E C E C/E C E C/E 103-MLA098-P 2.360E-7 (2.41 +/- 0.05)E-7 0.98 +/- 0.02 1.199E-3 (1.20 +/- 0.06)E-3 1.00 +/- 0.05 1.821E-3 (2.11 +/- 0.09)E-3 0.86 +/- 0.04 103-MLA098-BB 1.829E-7 (2.11 +/- 0.04)E-7 0.87 +/- 0.02 9.911E-4 (9.91 +/- 0.49)E-4 1.00 +/- 0.05 6.704E-4 (8.15 +/- 0.33)E-4 0.82 +/- 0.03 103-MLA098-JJ 1.163E-7 (1.23 +/- 0.02)E-7 0.95 +/- 0.02 6.537E-4 (6.67 +/- 0.33)E-4 0.98 +/- 0.05 1.224E-4 (1.64 +/- 0.07)E-4 0.75 +/- 0.03 104-MKP109-P 3.276E-7 (3.31 +/- 0.06)E-7 0.99 +/- 0.02 1.226E-3 (1.31 +/- 0.06)E-3 0.94 +/- 0.05 5.329E-3 (6.40 +/- 0.26)E-3 0.83 +/- 0.03 104-MKP109-CC 2.738E-7 (2.51 +/- 0.05)E-7 1.09 +/- 0.02 1.116E-3 (1.18 +/- 0.06)E-3 0.95 +/- 0.05 2.478E-3 (2.93 +/- 0.12)E-3 0.85 +/- 0.03 104-MKP109-LL 1.920E-7 (1.89 +/- 0.04)E-7 1.02 +/- 0.02 8.670E-4 (8.56 +/- 0.42)E-4 1.01 +/- 0.05 6.135E-4 (7.34 +/- 0.30)E-4 0.84 +/- 0.03 106-NBD107-Q 2.987E-7 (2.66 +/- 0.05)E-7 1.12 +/- 0.02 1.445E-3 (2.18 +/- 0.11)E-3 0.66 +/- 0.03 8.554E-3 (9.86 +/- 0.40)E-3 0.87 +/- 0.04 106-NBD107-GG 2.464E-7 (2.26 +/- 0.04)E-7 1.09 +/- 0.02 1.330E-3 (1.46 +/- 0.07)E-3 0.91 +/- 0.04 3.459E-3 (4.11 +/- 0.17)E-3 0.84 +/- 0.03 106-NBD107-MM 2.059E-7 (1.84 +/- 0.03)E-7 1.12 +/- 0.02 1.202E-3 (1.18 +/- 0.06)E-3 1.02 +/- 0.05 1.623E-3 (1.87 +/- 0.08)E-3 0.87 +/- 0.04 Mean ; SD 1.02 ; 0.09 0.94 ; 0.11 0.84 ; 0.04
Table 30: Calvert Cliffs results for Se79, Sr90 and Tc99.
Sample ID Se79/fuel (Ci/g) Sr90/fuel (Ci/g) Tc99/fuel (Ci/g) C E C/E C E C/E C E C/E 103-MLA098-P 2.835E-8 (5.54 +/- 0.27)E-8 5.12 +/- 0.25 5.225E-2 (5.23 +/- 0.30)E-2 1.00 +/- 0.06 1.193E-5 (1.13 +/- 0.04)E-5 1.06 +/- 0.04 103-MLA098-BB 2.329E-8 (4.59 +/- 0.22)E-8 5.07 +/- 0.25 4.428E-2 (4.41 +/- 0.25)E-2 1.00 +/- 0.06 9.857E-6 (9.37 +/- 0.33)E-6 1.05 +/- 0.04 103-MLA098-JJ 1.683E-8 (3.43 +/- 0.17)E-8 4.91 +/- 0.24 3.335E-2 (3.36 +/- 0.19)E-2 0.99 +/- 0.06 7.155E-6 (7.07 +/- 0.25)E-6 1.01 +/- 0.04 104-MKP109-P 3.697E-8 (6.49 +/- 0.32)E-8 5.70 +/- 0.28 6.754E-2 (6.58 +/- 0.38)E-2 1.03 +/- 0.06 1.525E-5 (1.35 +/- 0.05)E-5 1.13 +/- 0.04 104-MKP109-CC 3.168E-8 (6.036 +/- 0.296)E-8 5.25 +/- 0.26 5.955E-2 (5.90 +/- 0.34)E-2 1.01 +/- 0.06 1.320E-5 (1.23 +/- 0.04)E-5 1.07 +/- 0.04 104-MKP109-LL 2.411E-8 (4.55 +/- 0.22)E-8 5.30 +/- 0.26 4.723E-2 (4.59 +/- 0.26)E-2 1.03 +/- 0.06 1.015E-6 (9.59 +/- 0.34)E-6 1.06 +/- 0.04 106-NBD107-Q 3.774E-8 (5.99 +/- 0.29)E-8 6.30 +/- 0.31 6.147E-2 (6.04 +/- 0.34)E-2 1.02 +/- 0.06 1.557E-5 (1.09 +/- 0.04)E-5 1.43 +/- 0.05 106-NBD107-GG 3.124E-8 (5.63 +/- 0.28)E-8 5.55 +/- 0.27 5.308E-2 (5.18 +/- 0.30)E-2 1.02 +/- 0.06 1.308E-6 (8.96 +/- 0.31)E-6 1.46 +/- 0.05 106-NBD107-MM 2.690E-8 (4.18 +/- 0.20)E-8 6.43 +/- 0.32 4.708E-2 (4.64 +/- 0.26)E-2 1.01 +/- 0.06 1.133E-6 (7.70 +/- 0.27)E-6 1.47 +/- 0.05 Mean ; SD 5.51 ; 0.54 1.01 ; 0.01 1.19 ; 0.20
Table 31: Calvert Cliffs results for Sn126, Cs135 and Cs137.
Sample ID Sn126/fuel (Ci/g) Cs135/fuel (Ci/g) Cs137/fuel (Ci/g) C E C/E C E C/E C E C/E 103-MLA098-P 7.483E-7 (1.69 +/- 0.17)E-7 4.43 +/- 0.45 3.438E-7 (3.32 +/- 0.46)E-7 1.04 +/- 0.14 7.897E-2 (8.06 +/- 0.28)E-2 0.98 +/- 0.03 103-MLA098-BB 5.502E-7 (1.36 +/- 0.14)E-7 4.05 +/- 0.41 3.244E-7 (3.12 +/- 0.44)E-7 1.04 +/- 0.15 6.344E-2 (6.53 +/- 0.23)E-2 0.97 +/- 0.03 103-MLA098-JJ 3.377E-8 (8.60 +/- 0.88)E-8 3.93 +/- 0.40 2.896E-7 (2.79 +/- 0.39)E-7 1.04 +/- 0.15 4.458E-2 (4.59 +/- 0.16)E-2 0.97 +/- 0.03 104-MKP109-P 1.063E-7 (2.2 +/- 0.2)E-7 4.83 +/- 0.49 4.959E-7 (4.95 +/- 0.69)E-7 1.00 +/- 0.14 1.067E-1 (1.09 +/- 0.04)E-1 0.98 +/- 0.03 104-MKP109-CC 8.272E-7 (1.82 +/- 0.19)E-7 4.55 +/- 0.46 4.733E-7 (4.59 +/- 0.64)E-7 1.03 +/- 0.14 8.946E-2 (9.01 +/- 0.32)E-2 0.99 +/- 0.03 104-MKP109-LL 5.394E-7 (1.25 +/- 0.13)E-7 4.32 +/- 0.44 4.320E-7 (4.16 +/- 0.58)E-7 1.04 +/- 0.15 6.601E-2 (6.71 +/- 0.23)E-2 0.98 +/- 0.03 106-NBD107-Q 1.250E-7 (2.10 +/- 0.21)E-7 5.95 +/- 0.61 4.660E-7 (4.79 +/- 0.67)E-7 0.97 +/- 0.14 1.065E-1 (1.12 +/- 0.04)E-1 0.95 +/- 0.03 106-NBD107-GG 9.192E-7 (1.60 +/- 0.16)E-7 5.75 +/- 0.59 4.354E-7 (4.15 +/- 0.58)E-7 1.05 +/- 0.15 8.559E-2 (8.56 +/- 0.30)E-2 1.00 +/- 0.03 106-NBD107-MM 7.221E-7 (1.41 +/- 0.14)E-7 5.12 +/- 0.52 4.147E-7 (4.04 +/- 0.57)E-7 1.03 +/- 0.14 7.218E-2 (7.47 +/- 0.26)E-2 0.97 +/- 0.03 Mean ; SD 4.77 ; 0.71 1.03 ; 0.02 0.98 ; 0.01
21 Derived in this work by summing the isotopic results. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 62 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 32: Calvert Cliffs results for C14 and I129.
Sample ID C14/fuel (Ci/g) I129/fuel (Ci/g) CE C/ECEC/E 103-MLA098-E 5.276E-7 (5.40 +/- 0.30)E-7 0.98 +/- 0.05 103-MLA098-J 7.390E-7 (7.33 +/- 0.41)E-7 1.01 +/- 0.06 103-MLA098-S 2.804E-8 (3.36 +/- 0.07)E-8 0.83 +/- 0.02 103-MLA098-T 7.284E-7 (7.69 +/- 0.43)E-7 0.95 +/- 0.05 103-MLA098-DD 2.116E-8 (2.41 +/- 0.05)E-8 0.88 +/- 0.02 103-MLA098-EE 5.224E-7 (5.03 +/- 0.28)E-7 1.04 +/- 0.06 103-MLA098-LL 1.240E-8 (1.45 +/- 0.03)E-8 0.86 +/- 0.02 103-MLA098-MM 2.615E-7 (2.82 +/- 0.16)E-7 0.93 +/- 0.05 104-MKP109-E 6.781E-7 (9.00 +/- 0.50)E-7 0.75 +/- 0.04 104-MKP109-J 9.504E-7 (9.31 +/- 0.52)E-7 1.02 +/- 0.06 104-MKP109-T 3.792E-8 (3.75 +/- 0.08)E-8 1.01 +/- 0.02 104-MKP109-U 9.532E-6 (1.63 +/- 0.09)E-6 0.58 +/- 0.03 104-MKP109-FF 2.926E-8 (3.39 +/- 0.07)E-8 0.86 +/- 0.02 104-MKP109-GG 6.876E-7 (9.26 +/- 0.52)E-7 0.74 +/- 0.04 104-MKP109-OO 1.836E-8 (2.10 +/- 0.05)E-8 0.87 +/- 0.02 104-MKP109-PP 3.888E-7 (6.45 +/- 0.36)E-7 0.60 +/- 0.03 106-NBD107-E 1.022E-6 (1.038 +/- 0.058)E-6 0.98 +/- 0.06 106-NBD107-I 4.070E-6 (1.38 +/- 0.03)E-6 0.03 +/- 0.00 106-NBD107-U 4.084E-8 (3.83 +/- 0.08)E-8 1.07 +/- 0.02 106-NBD107-V 1.811E-6 (1.76 +/- 0.10)E-6 1.03 +/- 0.06 106-NBD107-BB 4.134E-8 (4.34 +/- 0.10)E-8 0.95 +/- 0.02 106-NBD107-CC 1.801E-6 (1.62 +/- 0.09)E-6 1.11 +/- 0.06 106-NBD107-PP 2.507E-8 (2.19 +/- 0.05)E-8 1.14 +/- 0.03 106-NBD107-QQ 9.350E-7 (5.40 +/- 0.30)E-7 1.73 +/- 0.10 Mean ; SD 0.96 ; 0.28 0.85 ; 0.31
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Table 33: Irradiation history of the Goesgen reactor.
Cycle Beginning of cycle End of cycle Duration of Duration of Cycle following (d) shutdown (d) 12 06/07/90 01/06/91 330 32 13 03/07/91 30/05/92 332 16 14 15/06/92 05/06/93 355 26 15 01/07/93 04/06/94 338 25 16 29/06/94 10/06/95 346 25 17 05/07/95 08/06/96 339 22 18 30/06/96 07/06/97 342
Table 34: Goesgen samples analysed as part of the Ariane programme.
Sample ID Cycles Assembly containing U234 Enrichment Height Sample Mean on- Derived Derived mean on- sample rod (% g/g) (U235% g/g) (mm) irradiation power rating irradiation22 power rating23 (MWd/t) (MW/t) (MWd/t) (MW/t) GU1 12-15 12-40 0.036 3.5 977.0 59656 44.03 58771 43.37 GU3’ and GU3 16-18 1601 (16+17), 1701 (18) 0.042 4.1 1274.2 52504 51.12 51790 and 49336 50.43 and 48.04 GU4 16-18 1601 (16+17), 1701 (18) 0.042 4.1 74.2 29067 28.30 30789 29.98
Table 35. Reported irradiation histories of the Goesgen samples (used in the WIMS models).
Sample Cycle Duration on Duration of Irradiation Mean cycle power shutdown (MWd/t) rating (d) (d) (MW/t) 12 330 32 18649 56.5121 13 332 16 33594 45.0151 GU1 14 355 26 47911 40.3296 15 338 59656 34.7485 16 346 25 21771 62.9220 GU3’ and GU3 17 339 22 38866 50.4277 18 342 52504 39.8772 16 346 25 11284 32.6127 GU4 17 339 22 21762 30.9086 18 342 29067 21.3596
Table 36. Average boron concentrations.
Sample Cycle Boron concentration (µg/g) 12 13 GU1 808.76 14 15 16 903.11 GU3’ and GU3 17 18 884.12 16 903.11 GU4 17 18 884.12
22 Derived in this work using measured Nd148/fuel (mg/g) ratio and FISPIN. 23 Derived in this work from derived irradiation and number of days on power. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 64 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 37: Goesgen results for the heavy nuclides.
Nuclide GU1 GU3' GU3 GU4 Mean ; SD U234/fuel (mg/g) 1.16 1.38 1.43 1.40 1.34 ; 0.12 U235/fuel (mg/g) 1.46 1.16 1.29 1.07 1.24 ; 0.17 U236/fuel (mg/g) 1.01 0.99 0.98 0.99 0.99 ; 0.01 U238/fuel (mg/g) 1.00 0.99 1.00 0.99 0.996 ; 0.001 Np237/fuel (mg/g) 0.85 0.79 0.70 0.78 ; 0.07 Pu238/fuel (mg/g) 0.98 0.92 0.85 1.00 0.94 ; 0.07 Pu239/fuel (mg/g) 1.20 1.07 1.07 1.10 1.11 ; 0.06 Pu240/fuel (mg/g) 0.96 0.96 0.93 0.97 0.96 ; 0.02 Pu241/fuel (mg/g) 1.16 1.08 1.05 1.08 1.09 ; 0.04 Pu242/fuel (mg/g) 0.82 0.91 0.83 0.94 0.87 ; 0.06 Pu244/fuel (mg/g) 0.67 0.52 0.60 ; 0.11 Pu/fuel (mg/g)24 1.07 1.03 1.00 1.06 1.04 ; 0.03 Am241/fuel (mg/g) 1.24 1.27 1.24 1.05 1.20 ; 0.10 Am242m/fuel (mg/g) 1.26 0.94 1.10 ; 0.23 Am243/fuel (mg/g) 1.01 1.03 0.79 1.00 0.95 ; 0.11 Cm242/fuel (mg/g) 0.97 0.92 0.95 ; 0.04 Cm243/fuel (mg/g) 3.07 1.16 2.11 ; 1.35 Cm244/fuel (mg/g) 0.89 0.82 0.55 0.76 0.76 ; 0.15 Cm245/fuel (mg/g) 0.97 0.76 0.49 0.73 0.74 ; 0.19 Cm246/fuel (mg/g) 0.61 0.63 0.62 ; 0.01
24 Derived in this work by summing the isotopic results. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 65 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 38: Goesgen results for the fission products.
Nuclide GU1 GU3' GU3 GU4 Mean ; SD Sr90/fuel (mg/g) 0.78 1.04 1.00 1.01 0.96 ; 0.12 Mo95/fuel (mg/g) 1.00 0.88 0.95 0.98 0.95 ; 0.05 Tc99/fuel (mg/g) 1.01 0.90 1.02 1.26 1.05 ; 0.15 Ru101/fuel (mg/g) 1.06 0.87 0.94 0.97 0.96 ; 0.08 Ru106/fuel (mg/g) 1.05 0.85 0.46 0.83 0.80 ; 0.25 Rh103/fuel (mg/g) 1.13 1.16 1.18 0.96 1.11 ; 0.10 Ag109/fuel (mg/g) 1.92 0.97 1.45 ; 0.67 Sb125/fuel (mg/g) 2.84 2.97 2.90 ; 0.09 I129/fuel (mg/g) 1.03 1.01 0.95 1.00 ; 0.04 Cs133/fuel (mg/g) 0.99 1.01 0.92 0.98 0.98 ; 0.04 Cs134/fuel (mg/g) 1.13 1.11 0.91 1.09 1.06 ; 0.10 Cs135/fuel (mg/g) 1.05 1.07 1.01 1.13 1.06 ; 0.05 Cs137/fuel (mg/g) 0.97 1.00 0.96 1.07 1.00 ; 0.05 Ce144/fuel (mg/g) 1.04 1.06 1.04 1.07 1.06 ; 0.01 Nd142/fuel (mg/g) 0.91 0.96 1.01 1.10 0.99 ; 0.08 Nd143/fuel (mg/g) 1.14 1.05 1.11 0.98 1.07 ; 0.07 Nd144/fuel (mg/g) 0.94 0.96 0.96 0.93 0.95 ; 0.02 Nd145/fuel (mg/g) 1.02 1.01 1.04 0.98 1.01 ; 0.02 Nd146/fuel (mg/g) 0.99 0.98 0.98 0.97 0.979 ; 0.005 Nd148/fuel (mg/g) 1.00 1.00 1.00 1.00 1.001 ; 0.002 Nd150/fuel (mg/g) 0.97 0.98 0.92 1.01 0.97 ; 0.03 Pm147/fuel (mg/g) 1.37 1.11 0.81 0.92 1.05 ; 0.25 Sm147/fuel (mg/g) 0.90 0.98 0.94 1.04 0.97 ; 0.06 Sm148/fuel (mg/g) 0.94 0.94 0.86 1.05 0.95 ; 0.08 Sm149/fuel (mg/g) 1.16 1.38 0.98 1.15 1.17 ; 0.17 Sm150/fuel (mg/g) 1.00 1.05 0.99 1.06 1.03 ; 0.03 Sm151/fuel (mg/g) 1.41 1.37 1.32 1.31 1.35 ; 0.05 Sm152/fuel (mg/g) 1.13 1.29 1.27 1.20 1.22 ; 0.07 Sm154/fuel (mg/g) 0.98 1.09 1.10 1.13 1.07 ; 0.07 Eu151/fuel (mg/g) 0.61 0.82 0.71 ; 0.15 Eu153/fuel (mg/g) 1.15 1.10 1.02 1.07 1.09 ; 0.05 Eu154/fuel (mg/g) 2.25 1.77 1.53 1.54 1.77 ; 0.33 Eu155/fuel (mg/g) 1.14 1.08 0.93 1.06 1.05 ; 0.09 Gd155/fuel (mg/g) 1.16 1.27 1.03 0.71 1.04 ; 0.24
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Table 39: Assembly information, irradiation, cooling and measured decay heat.
Reactor Clad Assembly Assembly U Enrichment Irradiation Duration of Shutdown Duration of Shutdown Duration of Mean rating25 Cooling Decay heat26 material mass cycle 1 cycle 2 cycle 3 (%) (GWd/t) (d) (d) (MW/t) (d) (W) (kg) (d) (d) (d) San Onofre SS C-01 362 3.865 26.540 672 153 384 216 436 17.79 3011 359 San Onofre SS C-16 362 3.865 28.462 672 153 384 216 436 19.08 2012 384 San Onofre SS C-16 362 3.865 28.462 672 153 384 216 436 19.08 2012 (458) San Onofre SS C-19 365 3.865 30.426 672 153 384 216 436 20.39 3011 418 San Onofre SS C-20 362 3.865 32.363 672 153 384 216 436 21.69 3011 456 San Onofre SS D-01 364 4.005 31.393 672 153 384 216 436 21.04 2358 499 San Onofre SS D-46 364 4.005 32.318 672 153 384 216 436 21.66 2360 510 San Onofre SS E-18 364 4.005 32.357 672 153 384 216 436 21.69 1794 635 San Onofre SS F-04 372 3.996 30.429 672 153 384 216 436 20.39 1078 934 WEPCO ZR C-52 386 3.397 31.914 671 120 385 104 319 23.21 1635 724 WEPCO ZR C-52 386 3.397 31.914 671 120 385 104 319 23.21 1635 723 WEPCO ZR C-56 386 3.397 38.917 671 120 385 104 319 28.30 1634 921 WEPCO ZR C-64 386 3.397 39.384 671 120 385 104 319 28.64 1633 931 WEPCO ZR C-64 386 3.397 39.384 671 120 385 104 319 28.64 1633 (825) WEPCO ZR C-66 386 3.397 35.433 671 120 385 104 319 25.77 1630 846 WEPCO ZR C-67 386 3.397 38.946 671 120 385 104 319 28.32 1629 934 WEPCO ZR C-68 386 3.397 37.057 671 120 385 104 319 26.95 1630 874 Turkey Point ZR D-04 457 2.556 28.430 284 111 284 111 283 33.41 913 (1385) Turkey Point ZR D-15 457 2.556 28.430 284 111 284 111 283 33.41 962 1423 Turkey Point ZR D-15 457 2.556 28.430 284 111 284 111 283 33.41 1144 (1126) Turkey Point ZR D-15 457 2.556 28.430 284 111 284 111 283 33.41 2077 625 Turkey Point ZR D-22 457 2.556 26.485 284 111 284 111 283 31.12 963 1284 Turkey Point ZR D-34 457 2.556 27.863 284 111 284 111 283 32.74 864 1550 Turkey Point ZR B-43 448 2.559 25.595 259 111 284 111 284 30.95 1782 637
25 The mean rating was calculated from the final irradiation and the number of on-power days. 26 Measurements in brackets were reported by Schmittroth as being suspect. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 67 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 40: FISPIN predictions of heat and their comparison with measured values.
Reactor Assembly Enrichment Irradiation Cooling Heavy element heat Fission product heat Fuel impurity heat Structural material Total heat for Measured C/E (%) (GWd/t) (d) (kW/tU) (kW/tU) (kW/tU) heat assembly heat27 (kW/tU) (W) (W) San Onofre C-01 3.865 26.540 3011 1.235E-01 7.757E-01 9.397E-04 1.400E-01 376.5 359 1.05 San Onofre C-16 3.865 28.462 3012 1.415E-01 8.336E-01 1.014E-03 1.512E-01 408.1 384 1.06 San Onofre C-16 3.865 28.462 3012 1.415E-01 8.336E-01 1.014E-03 1.512E-01 408.1 (458) (0.89) San Onofre C-19 3.865 30.426 3011 1.615E-01 8.933E-01 1.082E-03 1.615E-01 444.3 418 1.06 San Onofre C-20 3.865 32.363 3011 1.833E-01 9.524E-01 1.169E-03 1.745E-01 474.7 456 1.04 San Onofre D-01 4.005 31.393 2358 1.601E-01 1.068E+00 1.387E-03 2.077E-01 523.1 499 1.05 San Onofre D-46 4.005 32.318 2360 1.703E-01 1.102E+00 1.432E-03 2.144E-01 541.7 510 1.06 San Onofre E-18 4.005 32.357 1794 1.670E-01 1.365E+00 1.760E-03 2.649E-01 654.7 635 1.03 San Onofre F-04 3.996 30.429 1078 1.549E-01 2.101E+00 2.110E-03 3.212E-01 959.5 934 1.03 WEPCO C-52 3.397 31.914 1635 1.801E-01 1.525E+00 2.019E-03 1.313E-01 709.6 724 0.98 WEPCO C-52 3.397 31.914 1635 1.801E-01 1.525E+00 2.019E-03 1.313E-01 709.6 723 0.98 WEPCO C-56 3.397 38.917 1634 2.917E-01 1.948E+00 2.522E-03 1.643E-01 928.9 921 1.01 WEPCO C-64 3.397 39.384 1633 3.008E-01 1.978E+00 2.558E-03 1.666E-01 944.9 931 1.01 WEPCO C-64 3.397 39.384 1633 3.008E-01 1.978E+00 2.558E-03 1.666E-01 944.9 (825) (1.15) WEPCO C-66 3.397 35.433 1630 2.307E-01 1.739E+00 2.272E-03 1.479E-01 818.3 846 0.97 WEPCO C-67 3.397 38.946 1629 2.923E-01 1.956E+00 2.529E-03 1.647E-01 932.4 934 1.00 WEPCO C-68 3.397 37.057 1630 2.577E-01 1.838E+00 2.390E-03 1.556E-01 869.9 874 1.00 Turkey Point D-04 2.556 28.430 913 1.914E-01 3.168E+00 2.623E-03 1.139E-01 1588 (1385) (1.15) Turkey Point D-15 2.556 28.430 962 1.858E-01 2.970E+00 2.568E-03 1.116E-01 1494 1423 1.05 Turkey Point D-15 2.556 28.430 1144 1.731E-01 2.382E+00 2.380E-03 1.036E-01 1216 (1126) (1.08) Turkey Point D-15 2.556 28.430 2077 1.684E-01 1.160E+00 1.674E-03 7.275E-02 641.1 625 1.03 Turkey Point D-22 2.556 26.485 963 1.576E-01 2.712E+00 2.381E-03 1.034E-01 1360 1284 1.06 Turkey Point D-34 2.556 27.863 864 1.895E-01 3.301E+00 2.624E-03 1.139E-01 1648 1550 1.06 Turkey Point B-43 2.559 25.595 1782 1.317E-01 1.212E+00 1.709E-03 7.429E-02 636.0 637 1.00 Mean ; SD28 1.03 ; 0.03
27 Measurements in brackets were reported as being suspect. The quoted experimental error is 2%. 28 Excluding suspect measurements. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 68 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 41: Contributions to the decay heat of fission products, heavy elements, fuel impurities and structural materials.
Reactor Assembly Enrichment Irradiation Cooling Heavy element Fission product Fuel impurity Structural material (%) (GWd/t) (d) heat heat heat heat % % % % San Onofre C-01 3.865 26.540 3011 11.87 74.58 0.09 13.46 San Onofre C-16 3.865 28.462 2012 12.55 73.95 0.09 13.41 San Onofre C-16 3.865 28.462 2012 12.55 73.95 0.09 13.41 San Onofre C-19 3.865 30.426 3011 13.27 73.38 0.09 13.27 San Onofre C-20 3.865 32.363 3011 13.98 72.63 0.09 13.31 San Onofre D-01 4.005 31.393 2358 11.14 74.31 0.10 14.45 San Onofre D-46 4.005 32.318 2360 11.44 74.05 0.10 14.41 San Onofre E-18 4.005 32.357 1794 9.28 75.89 0.10 14.73 San Onofre F-04 3.996 30.429 1078 6.01 81.46 0.08 12.45 WEPCO C-52 3.397 31.914 1635 9.80 82.95 0.11 7.14 WEPCO C-52 3.397 31.914 1635 9.80 82.95 0.11 7.14 WEPCO C-56 3.397 38.917 1634 12.12 80.95 0.10 6.83 WEPCO C-64 3.397 39.384 1633 12.29 80.80 0.10 6.81 WEPCO C-64 3.397 39.384 1633 12.29 80.80 0.10 6.81 WEPCO C-66 3.397 35.433 1630 10.88 82.03 0.11 6.98 WEPCO C-67 3.397 38.946 1629 12.10 80.98 0.10 6.82 WEPCO C-68 3.397 37.057 1630 11.43 81.56 0.11 6.90 Turkey Point D-04 2.556 28.430 913 5.51 91.14 0.08 3.28 Turkey Point D-15 2.556 28.430 962 5.68 90.83 0.08 3.41 Turkey Point D-15 2.556 28.430 1144 6.50 89.51 0.09 3.89 Turkey Point D-15 2.556 28.430 2077 12.00 82.69 0.12 5.19 Turkey Point D-22 2.556 26.485 963 5.30 91.15 0.08 3.48 Turkey Point D-34 2.556 27.863 864 5.25 91.52 0.07 3.16 Turkey Point B-43 2.559 25.595 1782 9.28 85.37 0.12 5.23
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Table 42: Characteristics of the AGR samples.
29 Sample Enrichment Ring in Time on Cooling Sample UO2 Nd148/U238 Irradiation Mean on-power 30 (%) assembly power time mass (a/a) (MWd/t) rating (d) (d) (g) MW/t 31 2.55 Outer (3) 1218 763 168.48 4.1688E-4 22412.5 18.40 33 2.01 Outer (3) 1323 612 168.72 4.1809E-4 22476.9 16.99 34 2.55 Inner (1) 1218 763 168.66 3.4550E-4 18608.3 15.28 35 2.55 Middle (2) 1218 763 168.83 3.7226E-4 20036.1 16.45
Table 43: Comparison of calculated and experimental neutron emission rates from each sample.
Sample Calculated neutron emission rate Measured neutron emission rate C/E (neutron/s) (neutron/s) 31 7750 10306 +/- 206 0.75 +/- 0.02 33 15280 19282 +/- 386 0.79 +/- 0.02 34 4014 4845 +/- 97 0.83 +/- 0.02 35 4918 6091 +/- 121 0.81 +/- 0.02 Mean ; SD 0.80 ; 0.03
Table 44: Comparison of calculated and experimental values of Cm242 and Cm244 present in each sample.
Sample Cm242 (atom) Cm244 (atom) CEC/ECEC/E 31 8.488E16 1.041E17 0.815 1.443E18 1.891E18 0.763 33 2.142E17 2.484E17 0.862 2.843E18 3.749E18 0.758 34 5.388E16 6.432E16 0.838 6.954E17 7.620E17 0.913 35 6.158E16 7.337E16 0.839 8.730E17 1.016E18 0.859
29 Calculated in this work from Nd148/U238 (a/a) using FISPIN. 30 Derived in this work from calculated irradiation and days on power. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 70 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 45: Reactors and fuel parameters used for verification.
Fuel Type Generic Station Enrichment Rating Irradiation % MW/t GWd/t Magnox Wylfa natural 2.689 1 and 10 AGR Heysham 2 2.67 13.76 5 and 25 4.0 13.76 5 and 45 PWR Sizewell B 2.5 38.50 5 and 25 5.0 38.50 5 and 65
Table 46: Decay periods used in verification.
Reactor Decay Periods Magnox and AGR shutdown 10, 20, 100 days 1 – 10 years in steps of 1 year 20 – 100 years in steps of 10 years PWR shutdown 1 - 10 days in steps of 1 day 50 days - 1 year in steps of 50 days 10 - 50 years in steps of 10 years
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 71 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 47: The ratio of CASMO to WIMS predictions at shutdown.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 H3 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 1.00 Br84 0.98 0.99 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Kr83M 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Kr85 0.99 0.98 0.99 0.99 0.99 0.99 1.00 1.00 1.00 1.00 Kr85M 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Kr87 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Kr88 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Kr89 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.01 1.00 1.00 Rb86 1.01 0.88 1.07 0.95 1.10 0.91 1.00 0.98 1.00 0.98 Rb88 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Rb89 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Rb90 0.98 0.99 0.98 1.00 0.98 1.02 1.00 1.00 1.00 1.00 Rb91 0.98 0.99 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Sr89 0.98 0.99 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Sr90 0.99 0.98 0.99 0.99 0.99 0.99 1.00 1.00 1.00 1.00 Sr91 0.98 0.99 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 Sr92 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Y90 0.99 0.98 0.99 0.98 0.99 0.99 1.00 1.00 1.00 1.00 Y92 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Y93 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Y94 0.99 1.00 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Zr95 0.99 1.00 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Zr97 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Nb94 1.06 1.03 1.05 0.99 1.07 0.99 0.99 0.98 1.02 0.99 Nb95 1.00 1.00 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Nb97 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Nb97M 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Mo101 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Tc104 1.03 1.01 1.03 1.00 1.03 0.98 1.00 1.00 1.00 1.00 Ru103 1.02 1.00 1.02 1.00 1.02 0.99 1.00 1.00 1.00 1.00 Ru105 1.05 1.01 1.06 1.00 1.06 0.98 1.00 1.00 1.01 1.00 Ru106 1.05 1.01 1.07 1.03 1.07 1.00 1.00 1.00 1.01 1.00 Rh106 1.05 1.01 1.07 1.02 1.07 0.99 1.00 1.00 1.01 1.00 Ag108M 1.14 1.06 1.14 1.04 1.18 1.03 1.01 1.00 1.02 1.00 Ag110M 1.14 0.98 1.16 1.02 1.19 0.98 1.02 1.00 1.02 1.00 Sn127 1.05 1.02 1.04 1.01 1.04 0.99 1.00 1.00 1.00 1.00 Sb124 1.00 0.93 1.04 1.01 1.03 0.97 1.00 0.99 1.00 0.99 Sb125 1.05 1.02 1.05 1.03 1.05 1.01 1.00 1.00 1.01 1.00 Sb128 1.04 1.02 1.03 1.00 1.03 0.99 1.00 1.00 1.00 1.00 Sb128M 1.03 1.01 1.02 1.00 1.02 0.99 1.00 1.00 1.00 1.00 Sb129 1.01 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 Sb130M 1.01 1.01 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Sb131 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te131 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te132 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te133 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te134 0.99 0.99 0.99 1.00 1.00 1.01 1.00 1.00 1.00 1.00 I127 1.03 1.03 1.03 1.03 1.02 1.02 1.00 1.00 1.00 1.00 I129 1.01 1.02 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 I130 0.99 0.93 0.99 0.96 1.00 0.96 1.00 1.02 1.00 1.03 I131 1.01 1.00 1.01 1.00 1.01 0.99 1.00 1.00 1.00 1.00 I132 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I133 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I134 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I135 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I136 0.99 0.98 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe131M 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe133 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe133M 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe135 1.03 1.05 1.06 1.07 1.05 1.06 1.01 0.98 1.01 0.96 Xe135M 1.01 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 Xe137 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 72 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Xe138 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs133 1.00 1.00 1.00 1.00 1.00 1.01 1.00 1.00 1.00 1.00 Cs134 1.03 0.93 1.05 0.97 1.06 0.94 1.01 1.00 1.01 1.00 Cs135 1.02 1.04 1.05 1.06 1.05 1.06 1.01 1.00 1.01 1.00 Cs136 1.06 0.96 1.08 1.00 1.09 0.98 1.00 0.99 1.01 0.99 Cs137 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs138 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs139 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs140 0.99 0.99 0.99 1.00 1.00 1.01 1.00 1.00 1.00 1.00 Ba133 1.14 1.06 1.14 1.04 1.18 1.02 1.01 1.00 1.02 1.00 Ba137M 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba139 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba140 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba141 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La140 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La141 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La142 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ce143 0.99 1.00 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Ce144 0.99 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 Pr144 0.99 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 Pr146 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Pm147 1.00 1.01 1.00 1.01 1.00 1.03 1.00 1.00 1.00 1.00 Pm148 1.02 0.93 1.02 0.95 1.04 0.94 1.00 1.00 1.01 1.00 Pm148M 1.02 0.96 1.03 0.97 1.06 0.96 0.99 0.96 1.00 0.95 Pm150 0.98 0.93 0.98 0.93 0.99 0.93 1.00 1.02 1.00 1.04 Pm154 1.02 0.99 1.03 1.00 1.04 0.98 1.00 1.00 1.00 1.00 Eu152 1.00 1.11 1.05 1.13 1.05 1.15 1.01 0.98 1.00 0.96 Eu154 1.00 0.95 1.04 0.99 1.06 0.98 1.00 1.00 1.01 0.99 Eu155 1.05 0.99 1.06 0.97 1.07 0.93 0.99 0.97 1.00 0.96 Eu156 1.05 0.94 1.06 0.96 1.06 0.93 1.01 1.01 1.01 1.02 Ta182 0.95 0.94 1.14 1.11 1.20 1.08 0.99 0.99 1.03 1.00 Hg203 U234 0.96 0.73 0.93 0.69 0.95 0.57 0.92 0.64 0.95 0.41 U235 1.00 1.09 1.00 1.07 1.00 1.13 1.00 0.99 1.00 0.98 U236 0.99 0.98 1.01 0.99 1.01 0.99 1.00 1.00 1.00 0.98 U238 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Np239 1.11 1.02 1.07 0.96 1.11 0.93 0.98 0.97 0.99 0.98 Pu238 0.87 0.95 1.10 1.11 1.15 1.14 0.98 1.01 1.01 1.07 Pu239 1.11 1.08 1.06 0.95 1.10 0.91 0.97 0.94 0.99 0.92 Pu240 1.12 1.06 1.08 0.95 1.12 0.94 0.98 0.95 0.98 0.93 Pu241 1.11 1.03 1.32 1.07 1.39 1.01 0.99 0.97 0.99 0.95 Am241 1.11 1.08 1.33 1.11 1.40 1.05 0.99 0.97 0.99 0.94 Am243 1.11 0.90 1.47 1.02 1.57 0.89 1.02 0.98 1.01 0.87 Cm242 1.10 1.00 1.41 1.16 1.50 1.10 1.00 1.00 0.99 0.98 Cm243 1.09 0.94 1.49 1.17 1.63 1.12 0.99 0.98 0.98 0.97 Cm244 1.08 0.82 1.48 1.01 1.62 0.88 1.02 0.99 1.01 0.91 Total 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Decay Heat Fission product 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Heavy nuclide 1.11 1.02 1.07 0.97 1.11 0.94 0.98 0.97 0.99 0.98 Neutron Total 1.10 0.96 1.32 1.11 1.33 0.98 0.99 1.00 0.99 0.93 Emission Spontaneous fission 1.10 0.96 1.33 1.11 1.36 0.97 0.99 1.00 0.99 0.93 (n/s) Alpha-n 1.26 1.15 1.26 1.09 0.99 1.00 0.99 0.98 Gamma Total 1.02 1.00 1.01 0.99 1.01 0.99 1.00 0.99 1.00 0.99 emission Fission product 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 (γ/s) Heavy nuclide 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 Gamma Total 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 emission Fission product 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 (MeV/s) Heavy nuclide 1.11 1.02 1.07 0.97 1.11 0.94 0.98 0.97 0.98 0.99
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 73 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 48: The ratio of CASMO to WIMS predictions at the maximum cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 H3 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Br84 Kr83M 1.00 1.00 1.00 1.00 Kr85 Kr85M 1.00 1.00 1.00 1.00 Kr87 1.00 1.00 1.00 1.00 Kr88 Kr89 1.00 1.00 1.00 1.00 Rb86 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Rb88 1.00 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 Rb89 Rb90 1.00 1.01 1.00 1.01 1.00 1.03 1.00 1.00 1.00 1.00 Rb91 0.96 1.03 0.97 1.06 0.96 1.00 1.00 1.01 1.00 Sr89 0.96 1.03 0.97 1.06 0.96 0.99 0.96 1.00 0.95 Sr90 1.00 1.02 1.00 1.04 Sr91 Sr92 1.00 1.11 1.05 1.13 1.05 1.15 1.00 0.98 1.00 0.96 Y90 1.00 0.95 1.04 0.99 1.06 0.98 1.00 1.00 1.01 0.99 Y92 1.05 0.99 1.06 0.97 1.07 0.93 0.99 0.97 1.00 0.96 Y93 1.01 1.01 1.01 1.02 Y94 0.94 0.94 1.14 1.10 1.20 1.07 0.99 0.99 1.03 1.00 Zr95 Zr97 0.96 0.74 0.93 0.70 0.95 0.60 0.92 0.64 0.95 0.41 Nb94 1.00 1.09 1.00 1.07 1.00 1.13 1.00 0.99 1.00 0.98 Nb95 0.99 0.98 1.00 0.99 1.01 0.99 1.00 1.00 1.00 0.98 Nb97 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Nb97M 1.11 0.90 1.47 1.02 1.57 0.89 0.98 0.98 0.99 0.98 Mo101 0.88 0.96 1.11 1.12 1.16 1.13 0.98 1.01 1.01 1.07 Tc104 1.11 1.08 1.06 0.95 1.10 0.91 0.97 0.94 0.99 0.92 Ru103 1.12 1.06 1.08 0.95 1.12 0.94 0.98 0.95 0.98 0.93 Ru105 1.11 1.03 1.32 1.07 1.39 1.01 0.99 0.97 0.99 0.95 Ru106 1.11 1.04 1.32 1.08 1.39 1.02 0.99 0.97 0.99 0.94 Rh106 1.11 0.90 1.47 1.02 1.58 0.89 1.02 0.98 1.01 0.87 Ag108M 1.11 1.07 1.43 1.19 1.52 1.12 1.00 1.00 0.99 0.98 Ag110M 1.09 0.94 1.49 1.17 1.63 1.12 0.99 0.98 0.99 0.97 Sn127 1.08 0.82 1.48 1.01 1.62 0.88 1.02 0.99 1.01 0.91 Sb124 1.00 0.93 1.04 1.01 1.03 0.97 1.00 0.99 1.00 0.99 Sb125 1.05 1.02 1.05 1.03 1.05 1.01 1.00 1.00 1.01 1.00 Sb128 1.04 1.02 1.03 1.00 1.03 0.99 1.00 1.00 1.00 1.00 Sb128M 1.03 1.01 1.02 1.00 1.02 0.99 1.00 1.00 1.00 1.00 Sb129 1.01 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 Sb130M 1.01 1.01 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Sb131 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te131 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te132 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te133 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Te134 0.99 0.99 0.99 1.00 1.00 1.01 1.00 1.00 1.00 1.00 I127 1.03 1.03 1.03 1.03 1.02 1.02 1.00 1.00 1.00 1.00 I129 1.01 1.02 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 I130 0.99 0.93 0.99 0.96 1.00 0.96 1.00 1.02 1.00 1.03 I131 1.01 1.00 1.01 1.00 1.01 0.99 1.00 1.00 1.00 1.00 I132 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I133 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I134 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I135 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 I136 0.99 0.98 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe131M 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe133 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe133M 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Xe135 1.03 1.05 1.06 1.07 1.05 1.06 1.01 0.98 1.01 0.96 Xe135M 1.01 1.01 1.01 1.00 1.01 1.00 1.00 1.00 1.00 1.00 Xe137 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 74 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Xe138 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs133 1.00 1.00 1.00 1.00 1.00 1.01 1.00 1.00 1.00 1.00 Cs134 1.03 0.93 1.05 0.97 1.06 0.94 1.01 1.00 1.01 1.00 Cs135 1.02 1.04 1.05 1.06 1.05 1.06 1.01 1.00 1.01 1.00 Cs136 1.06 0.96 1.08 1.00 1.09 0.98 1.00 0.99 1.01 0.99 Cs137 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs138 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs139 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Cs140 0.99 0.99 0.99 1.00 1.00 1.01 1.00 1.00 1.00 1.00 Ba133 1.14 1.06 1.14 1.04 1.18 1.02 1.01 1.00 1.02 1.00 Ba137M 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba139 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba140 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ba141 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La140 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La141 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 La142 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Ce143 0.99 1.00 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 Ce144 0.99 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 Pr144 0.99 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 Pr146 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Pm147 1.00 1.01 1.00 1.01 1.00 1.03 1.00 1.00 1.00 1.00 Pm148 1.02 0.93 1.02 0.95 1.04 0.94 1.00 1.00 1.01 1.00 Pm148M 1.02 0.96 1.03 0.97 1.06 0.96 0.99 0.96 1.00 0.95 Pm150 0.98 0.93 0.98 0.93 0.99 0.93 1.00 1.02 1.00 1.04 Pm154 1.02 0.99 1.03 1.00 1.04 0.98 1.00 1.00 1.00 1.00 Eu152 1.00 1.11 1.05 1.13 1.05 1.15 1.01 0.98 1.00 0.96 Eu154 1.00 0.95 1.04 0.99 1.06 0.98 1.00 1.00 1.01 0.99 Eu155 1.05 0.99 1.06 0.97 1.07 0.93 0.99 0.97 1.00 0.96 Eu156 1.05 0.94 1.06 0.96 1.06 0.93 1.01 1.01 1.01 1.02 Ta182 0.95 0.94 1.14 1.11 1.20 1.08 0.99 0.99 1.03 1.00 Hg203 U234 0.96 0.73 0.93 0.69 0.95 0.57 0.92 0.64 0.95 0.41 U235 1.00 1.09 1.00 1.07 1.00 1.13 1.00 0.99 1.00 0.98 U236 0.99 0.98 1.01 0.99 1.01 0.99 1.00 1.00 1.00 0.98 U238 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Np239 1.11 1.02 1.07 0.96 1.11 0.93 0.98 0.97 0.99 0.98 Pu238 0.87 0.95 1.10 1.11 1.15 1.14 0.98 1.01 1.01 1.07 Pu239 1.11 1.08 1.06 0.95 1.10 0.91 0.97 0.94 0.99 0.92 Pu240 1.12 1.06 1.08 0.95 1.12 0.94 0.98 0.95 0.98 0.93 Pu241 1.11 1.03 1.32 1.07 1.39 1.01 0.99 0.97 0.99 0.95 Am241 1.11 1.08 1.33 1.11 1.40 1.05 0.99 0.97 0.99 0.94 Am243 1.11 0.90 1.47 1.02 1.57 0.89 1.02 0.98 1.01 0.87 Cm242 1.10 1.00 1.41 1.16 1.50 1.10 1.00 1.00 0.99 0.98 Cm243 1.09 0.94 1.49 1.17 1.63 1.12 0.99 0.98 0.98 0.97 Cm244 1.08 0.82 1.48 1.01 1.62 0.88 1.02 0.99 1.01 0.91 Total 1.05 0.99 1.00 1.00 1.00 0.99 1.00 1.00 1.00 1.00 Decay Heat Fission product 0.99 0.99 1.00 0.99 1.00 0.99 1.00 1.00 1.00 1.00 Heavy nuclide 1.11 1.01 1.12 1.06 1.16 1.01 0.98 0.99 0.99 0.99 Neutron Total 1.10 0.85 1.11 1.01 1.14 0.88 0.99 1.00 0.99 0.93 Emission Spontaneous fission 1.10 0.85 1.10 1.01 1.12 0.88 0.99 0.99 0.99 0.93 (n/s) Alpha-n 1.13 1.06 1.16 1.01 0.99 1.00 0.99 0.98 Gamma Total 1.01 0.99 1.01 1.00 1.01 0.99 1.00 1.00 1.00 1.00 emission Fission product 1.00 0.99 1.01 0.99 1.01 0.99 1.00 1.00 1.00 1.00 (γ/s) Heavy nuclide 1.11 1.03 1.25 1.07 1.29 1.02 0.98 0.99 0.99 1.01 Gamma Total 1.00 0.99 1.00 0.99 1.00 0.98 1.00 1.00 1.00 1.00 emission Fission product 1.00 0.99 1.00 0.99 1.00 0.98 1.00 1.00 1.00 1.00 (MeV/s) Heavy nuclide 1.11 1.03 1.28 1.07 1.34 1.01 0.98 0.98 0.99 1.01
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 75 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 49: Summary of the ratio CASMO to WIMS predictions over all cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Min – Max 0.94 - 1.14 0.88 - 1.11 0.98 - 1.16 0.93 - 1.13 0.98 - 1.20 0.91 - 1.15 0.99 - 1.02 0.96 - 1.04 1.00 - 1.03 0.95 - 1.04 Fission Products Mean ; SD 1.02 ; 0.04 1.00 ; 0.04 1.03 ; 0.05 1.01 ; 0.03 1.04 ; 0.06 1.00 ; 0.04 1.00 ; 0.01 1.00 ; 0.01 1.00 ; 0.01 1.00 ; 0.01 Min – Max 0.87 - 1.12 0.73 - 1.09 0.93 - 1.49 0.69 - 1.20 0.95 - 1.63 0.57 - 1.14 0.92 - 1.02 0.64 - 1.01 0.95 - 1.01 0.41 - 1.07 Heavy Nuclides Mean ; SD 1.06 ; 0.07 0.97 ; 0.10 1.22 ; 0.21 1.02 ; 0.11 1.28 ; 0.25 0.98 ; 0.13 0.99 ; 0.02 0.96 ; 0.09 0.99 ; 0.02 0.92 ; 0.14 Min – Max 1.00 - 1.05 0.99 - 1.02 1.00 - 1.06 1.00 - 1.03 1.00 - 1.05 0.99 - 1.02 1.00 - 1.00 0.99 - 1.00 1.00 - 1.00 0.99 - 1.00 Decay Heat Mean ; SD 1.01 ; 0.01 1.00 ; 0.01 1.01 ; 0.02 1.01 ; 0.01 1.01 ; 0.02 1.00 ; 0.01 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00 Neutron Emission Min – Max 1.10 - 1.10 0.85 - 1.01 1.10 - 1.32 1.01 - 1.11 1.13 - 1.33 0.88 - 0.98 0.98 - 0.99 0.99 - 1.00 0.99 - 0.99 0.92 - 0.93 (n/s) Mean ; SD 1.10 ; 0.00 0.90 ; 0.06 1.16 ; 0.07 1.04 ; 0.04 1.18 ; 0.07 0.91 ; 0.04 0.99 ; 0.00 0.99 ; 0.00 0.99 ; 0.00 0.93 ; 0.01 Gamma emission Min – Max 1.00 - 1.02 0.98 - 1.01 1.00 - 1.02 0.99 - 1.01 1.00 - 1.02 0.97 - 1.00 0.99 - 1.00 0.99 - 1.00 0.99 - 1.00 0.99 - 1.00 (γ/s) Mean ; SD 1.01 ; 0.00 1.00 ; 0.01 1.01 ; 0.01 1.00 ; 0.01 1.01 ; 0.00 0.99 ; 0.01 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00 Gamma emission Min – Max 1.00 - 1.01 0.98 - 1.00 1.00 - 1.02 0.99 - 1.00 1.00 - 1.02 0.97 - 1.00 1.00 - 1.00 1.00 - 1.00 1.00 - 1.00 1.00 - 1.00 (MeV/s) Mean ; SD 1.00 ; 0.00 0.99 ; 0.01 1.00 ; 0.01 1.00 ; 0.00 1.00 ; 0.01 0.99 ; 0.01 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00 1.00 ; 0.00
Table 50: Gamma groups used in FISPIN and SCALE.
Group Energy Range (MeV) FISPIN SCALE 1 0.0-0.01 0.0-0.02 2 0.01-0.02 0.02-0.04 3 0.02-0.05 0.04-0.07 4 0.05-0.1 0.07-0.1 5 0.1-0.2 0.1-0.14 6 0.2-0.3 0.14-0.2 7 0.3-0.4 0.2-0.4 8 0.4-0.6 0.4-0.9 9 0.6-0.8 0.9-1.35 10 0.8-1.0 1.35-1.8 11 1.0-1.22 1.8-2.2 12 1.22-1.44 2.2-2.6 13 1.44-1.66 2.6-3.0 14 1.66-2.0 3.0-3.5 15 2.0-2.5 3.5-4.0 16 2.5-3.0 4.0-4.5 17 3.0-4.0 4.5-5.0 18 4.0-5.0 5.0-6.0 19 5.0-6.5 20 6.5-8.0 21 8.0-10.0 22 10.0-12.0 23 12.0-14.0 24 14.0–>
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 76 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 51: The ratio of CASMO to WIMS predictions of the gamma spectrum (γ/s) at shutdown.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 1 1.06 1.01 1.03 0.98 1.04 0.97 0.99 0.99 0.99 0.99 2 1.09 1.01 1.05 0.97 1.08 0.95 0.98 0.98 0.99 0.99 3 1.01 1.00 1.00 1.00 1.01 0.99 1.00 1.00 1.00 1.00 4 1.07 1.01 1.04 0.98 1.05 0.96 0.99 0.98 0.99 0.99 5 1.04 1.00 1.02 0.99 1.03 0.97 0.99 0.99 1.00 0.99 6 1.02 1.00 1.01 0.99 1.02 0.98 0.99 0.99 1.00 0.99 7 1.00 0.99 1.00 1.00 1.01 0.99 1.00 1.00 1.00 1.00 /s)
γ 8 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 9 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 10 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 11 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 12 0.99 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 13 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 14 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Total gamma emission ( 15 0.99 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 16 0.99 0.99 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 17 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 18 0.98 0.98 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 19 0.98 0.98 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 20 0.98 0.98 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 21 0.97 0.99 0.97 1.00 0.97 1.07 1.00 1.02 1.00 1.03 1 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 2 1.00 1.00 1.01 1.00 1.01 0.99 1.00 1.00 1.00 1.00 3 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4 1.00 0.99 1.01 1.00 1.01 0.99 1.00 1.00 1.00 1.00 5 0.99 0.98 1.00 1.00 1.00 0.99 1.00 1.00 1.00 0.99 6 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 /s) γ 7 1.00 0.99 1.00 1.00 1.00 0.99 1.00 1.00 1.00 1.00 8 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 9 1.00 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 10 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 11 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 12 0.99 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 13 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 14 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 15 0.99 0.99 0.99 1.00 1.00 1.00 1.00 1.00 1.00 1.00
Fission gamma emission product ( 16 0.99 0.99 0.99 1.00 0.99 1.00 1.00 1.00 1.00 1.00 17 0.99 0.99 0.99 1.00 0.99 1.01 1.00 1.00 1.00 1.00 18 0.98 0.98 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 19 0.98 0.98 0.99 1.00 0.99 1.02 1.00 1.00 1.00 1.00 20 0.98 0.98 0.98 1.00 0.99 1.02 1.00 1.00 1.00 1.00 21 0.97 0.99 0.97 1.00 0.97 1.07 1.00 1.02 1.00 1.03 1 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 2 1.11 1.02 1.07 0.97 1.11 0.94 0.98 0.98 0.99 0.98 3 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 4 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 5 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 6 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 7 1.11 1.02 1.07 0.96 1.11 0.94 0.98 0.98 0.99 0.98 8 1.09 0.99 1.03 0.91 1.08 0.88 0.87 0.85 0.90 0.86 9 1.10 1.01 1.06 0.95 1.10 0.92 0.95 0.94 0.96 0.94 10 1.09 0.98 1.05 0.97 1.10 0.98 0.92 0.94 0.94 1.03 11 1.03 0.85 1.05 1.03 1.10 1.05 0.89 1.00 0.92 1.10 12 1.11 0.92 1.12 0.92 1.20 0.86 0.98 0.97 0.99 0.97 13 1.11 0.92 1.12 0.92 1.20 0.86 0.98 0.97 0.99 0.97 Heavy nuclide gamma emission (g/s) 14 1.11 0.92 1.12 0.92 1.20 0.86 0.98 0.97 0.99 0.97 15 0.99 0.91 0.98 0.89 0.98 0.79 0.99 0.98 0.98 0.91 16 0.93 0.68 1.01 0.82 1.06 0.78 0.95 0.67 1.01 0.58 17 0.99 0.91 0.98 0.89 0.98 0.86 0.97 0.87 0.98 0.79
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 77 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 52: The ratio of CASMO to WIMS predictions of the gamma spectrum (γ/s) at the maximum cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 1 1.04 1.02 1.10 1.04 1.08 1.01 1.00 0.99 1.00 0.98 2 1.11 1.03 1.27 1.07 1.33 1.02 0.99 0.97 0.99 0.97 3 1.00 1.00 1.01 1.01 1.01 1.00 1.00 1.00 1.00 1.00 4 1.11 1.03 1.31 1.07 1.39 1.01 0.99 0.97 0.99 0.95 5 1.05 0.94 1.14 1.03 1.11 0.92 1.00 0.99 1.01 0.97 /s)
γ 6 1.04 0.91 1.16 1.03 1.10 0.91 1.00 0.99 1.01 0.95 7 1.04 0.94 1.12 1.04 1.14 0.93 0.99 0.99 1.00 0.92 8 1.04 1.02 1.03 1.02 1.03 1.01 1.00 1.00 1.00 0.99 9 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 10 1.01 0.96 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99 11 1.00 0.96 1.03 0.99 1.04 0.98 1.00 1.00 1.01 0.99 12 1.00 0.95 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99 Total gamma emission ( 13 1.01 0.95 1.03 0.99 1.05 0.98 1.00 1.00 1.01 0.99 14 0.99 0.98 0.99 0.99 0.99 0.99 1.00 1.00 1.00 1.00 15 0.96 0.78 0.93 0.73 0.95 0.68 0.92 0.67 0.95 0.60 16 0.71 0.55 0.75 0.60 0.86 0.62 0.56 0.42 0.71 0.46 17 0.96 0.78 0.93 0.73 0.95 0.68 0.92 0.67 0.95 0.60 1 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 2 0.99 0.99 0.99 0.99 0.99 0.99 1.00 1.00 1.00 1.00 3 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 4 1.04 1.03 1.04 1.03 1.03 1.02 1.00 0.99 1.00 0.99 /s) γ 5 1.00 0.95 1.04 0.99 1.06 0.98 1.00 1.00 1.01 0.99 6 1.01 0.96 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99 7 1.00 1.08 1.05 1.08 1.05 1.07 1.00 1.00 1.01 0.99 8 1.03 1.02 1.03 1.02 1.03 1.01 1.00 1.00 1.00 0.99 9 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 10 1.01 0.96 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99 11 1.01 0.96 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99 12 1.00 0.95 1.04 0.99 1.06 0.98 1.00 1.00 1.01 0.99 13 1.01 0.96 1.04 0.99 1.05 0.98 1.00 1.00 1.01 0.99
Fission gamma emission product ( 14 0.99 0.98 0.99 0.99 0.99 0.99 1.00 1.00 1.00 1.00 15 1.02 1.00 1.14 1.06 1.19 1.05 1.00 1.00 1.01 1.00 16 1.02 1.00 1.14 1.06 1.19 1.05 1.00 1.00 1.01 1.00 17 1.05 1.01 1.07 1.03 1.07 1.00 1.00 1.00 1.01 1.00 1 1.11 1.03 1.25 1.07 1.30 1.02 0.99 0.97 0.99 0.97 2 1.11 1.03 1.27 1.07 1.33 1.02 0.99 0.97 0.99 0.97 3 1.11 1.03 1.31 1.07 1.39 1.01 0.99 0.97 0.99 0.95 4 1.11 1.03 1.32 1.07 1.39 1.01 0.99 0.97 0.99 0.95 /s) γ 5 1.06 0.94 1.16 1.04 1.11 0.91 0.99 0.98 1.00 0.89 6 1.04 0.91 1.21 1.03 1.12 0.91 1.00 0.98 0.99 0.89 7 1.05 0.94 1.12 1.04 1.15 0.93 0.98 0.99 1.00 0.90 8 1.09 1.00 1.08 0.98 1.11 0.89 0.96 0.85 0.97 0.73 9 1.01 1.02 1.13 1.06 1.11 0.99 0.99 0.95 0.99 0.88 10 1.00 1.06 1.03 1.13 1.02 1.05 0.98 0.89 0.99 0.81 11 1.00 1.05 1.01 1.11 1.00 1.08 1.00 0.97 1.00 0.91 12 1.00 0.99 0.99 0.98 0.99 0.95 1.00 0.97 1.00 0.84 13 1.00 0.93 0.99 0.82 0.99 0.71 0.97 0.57 0.98 0.48 Heavy nuclide gamma emission ( 14 1.00 0.99 1.00 0.97 1.00 0.92 1.00 0.91 1.00 0.67 15 0.96 0.78 0.93 0.73 0.95 0.68 0.92 0.67 0.95 0.60 16 0.71 0.55 0.75 0.60 0.86 0.62 0.56 0.42 0.71 0.46 17 0.96 0.78 0.93 0.73 0.95 0.68 0.92 0.67 0.95 0.60
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 78 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 53: The ratio of SCALE to WIMS predictions at shutdown.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 H3 1.09 1.05 1.10 1.06 1.10 1.06 1.10 1.06 1.11 1.05 Br84 Kr83M 0.99 0.99 0.99 0.99 Kr85 0.92 0.89 0.93 0.92 0.94 0.91 0.91 0.91 0.92 0.90 Kr85M 0.92 0.90 0.93 0.89 Kr87 0.99 0.98 1.00 0.98 Kr88 1.02 1.01 1.03 0.99 Kr89 Rb86 0.51 0.75 0.23 0.29 0.20 0.30 0.73 0.80 0.73 0.84 Rb88 1.03 1.01 1.05 1.00 Rb89 Rb90 Rb91 Sr89 1.02 0.99 1.03 1.00 1.04 0.96 1.03 1.01 1.04 1.02 Sr90 1.01 0.98 1.02 1.01 1.03 1.00 1.01 1.01 1.02 1.01 Sr91 1.00 0.99 1.02 0.99 Sr92 0.99 0.98 1.00 0.97 Y90 1.04 1.02 1.05 1.04 1.06 1.04 1.02 1.05 1.03 1.05 Y92 1.00 0.98 1.01 0.98 Y93 0.67 0.65 0.68 0.65 Y94 Zr95 1.00 0.98 1.00 0.99 1.01 0.98 1.00 0.99 1.00 0.98 Zr97 0.96 0.96 0.96 0.94 0.96 0.93 0.96 0.96 0.96 0.95 Nb94 1.30 0.97 1.04 0.81 1.09 0.78 0.61 0.33 0.63 0.29 Nb95 0.99 0.98 1.00 0.99 1.01 0.98 1.00 0.99 1.01 0.99 Nb97 0.97 0.94 0.97 0.93 0.96 0.96 0.96 0.95 Nb97M 0.96 0.96 0.96 0.95 Mo101 Tc104 Ru103 1.03 1.00 1.03 1.00 1.03 1.00 1.04 1.02 1.04 0.99 Ru105 1.03 0.97 1.04 0.96 Ru106 1.06 1.05 1.07 1.08 1.04 1.09 1.06 1.05 1.04 1.03 Rh106 Ag108M 3.09 5.44 14.55 72.61 15.99 166.71 Ag110M 1.02 0.92 0.44 0.46 0.39 0.49 1.03 0.91 1.10 0.89 Sn127 0.70 0.62 0.67 0.58 Sb124 0.23 0.50 0.13 0.17 0.10 0.17 0.38 0.57 0.32 0.54 Sb125 0.78 0.55 0.84 0.61 0.90 0.56 0.85 0.58 0.94 0.52 Sb128 1.15 1.07 1.12 1.01 Sb128M Sb129 1.14 1.09 1.11 1.05 Sb130M Sb131 Te131 0.92 0.91 0.98 0.93 0.99 0.91 Te132 1.03 1.02 1.03 1.00 1.03 1.00 1.03 1.01 1.02 1.00 Te133 Te134 I127 1.04 1.03 1.08 1.06 1.07 1.03 1.02 1.00 1.01 0.94 I129 1.03 1.05 1.02 1.03 1.01 1.03 1.03 1.03 1.01 1.00 I130 0.96 0.91 1.01 0.90 I131 1.00 0.99 1.01 0.98 1.01 0.97 1.01 0.98 1.01 0.96 I132 1.02 1.02 1.02 1.00 1.02 0.99 1.03 1.01 1.03 1.00 I133 1.02 1.00 1.03 0.99 1.03 0.99 1.02 1.00 1.02 0.99 I134 I135 1.01 1.01 1.01 0.99 I136 Xe131M 1.01 1.08 1.04 1.00 1.04 1.10 1.05 1.18 1.05 1.38 Xe133 0.99 1.01 0.98 0.99 0.98 0.99 1.02 0.97 1.03 0.96 Xe133M 1.06 1.08 0.98 1.04 0.98 1.03 1.05 1.06 1.04 1.04 Xe135 1.02 1.01 1.01 0.99 Xe135M 1.00 1.00 1.00 1.00 Xe137
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 79 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Xe138 Cs133 Cs134 0.91 0.88 1.10 1.07 1.11 1.04 0.91 0.87 0.91 0.82 Cs135 1.02 1.04 1.04 1.06 1.03 1.06 1.01 1.03 1.01 1.03 Cs136 0.92 0.97 0.70 0.62 0.61 0.59 0.92 0.93 0.90 0.95 Cs137 1.02 1.03 1.03 1.03 1.03 1.03 1.02 1.03 1.02 1.03 Cs138 Cs139 Cs140 Ba133 Ba137M 1.03 1.03 1.03 1.04 1.03 1.04 1.03 1.04 1.03 Ba139 1.01 1.02 1.02 1.02 Ba140 1.02 1.03 1.03 1.02 1.03 1.01 1.02 1.03 1.02 1.03 Ba141 La140 1.04 1.03 1.08 1.01 1.08 1.00 1.02 1.06 1.03 1.05 La141 0.99 0.99 1.00 0.97 La142 1.01 0.98 1.02 0.97 Ce143 1.00 0.98 1.01 0.97 1.01 0.96 1.00 0.98 1.01 0.98 Ce144 1.01 1.00 1.02 1.00 1.02 0.99 1.01 1.01 1.02 1.00 Pr144 1.01 1.00 1.02 1.00 1.02 0.99 1.01 1.01 1.02 1.00 Pr146 Pm147 0.97 1.00 0.96 0.93 0.96 0.89 1.01 1.00 1.01 1.02 Pm148 0.90 0.91 1.05 1.04 1.07 1.03 0.95 0.89 0.95 0.88 Pm148M 1.07 1.04 1.59 1.51 1.60 1.47 0.96 0.83 0.89 0.74 Pm150 1.04 1.05 1.06 1.06 Pm154 Eu152 1.94 2.06 2.14 2.46 2.10 2.36 1.89 1.91 1.81 1.69 Eu154 0.94 0.59 0.99 0.60 1.07 0.49 0.90 0.68 0.98 0.62 Eu155 0.93 1.05 0.73 1.01 0.67 0.95 0.68 0.70 0.62 0.58 Eu156 1.05 1.16 1.15 1.46 1.17 1.43 1.14 1.12 1.25 1.09 Ta182 Hg203 U234 1.00 1.00 0.99 0.95 0.99 0.91 1.00 1.00 1.00 1.03 U235 1.00 0.99 0.99 0.90 1.00 0.80 0.99 0.97 0.99 0.92 U236 1.03 1.03 1.07 1.07 1.08 1.06 1.04 1.03 1.05 1.02 U238 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Np239 0.99 1.01 1.03 1.07 1.02 1.10 1.01 1.00 1.00 1.01 Pu238 0.93 0.92 1.10 1.27 1.10 1.26 1.07 1.08 1.07 1.09 Pu239 0.99 1.00 0.98 0.87 0.99 0.85 0.98 0.97 0.98 0.96 Pu240 1.00 1.00 1.15 1.11 1.14 1.06 1.01 1.03 1.01 1.03 Pu241 0.96 0.98 1.08 1.02 1.13 0.99 0.97 0.99 0.99 0.96 Am241 0.94 1.00 1.10 0.91 1.16 0.82 0.95 1.00 0.97 0.99 Am243 1.15 1.11 1.78 1.47 1.90 1.30 1.24 1.25 1.30 1.18 Cm242 0.83 0.88 1.14 1.05 1.21 0.98 0.84 0.92 0.86 0.92 Cm243 0.95 1.61 1.33 1.74 1.19 1.01 1.09 1.06 1.06 Cm244 1.07 0.98 1.96 1.72 2.09 1.59 1.19 1.17 1.26 1.13 Total 1.00 0.99 1.00 0.98 1.01 0.97 1.00 0.99 1.01 0.98 Decay Heat Fission product 1.00 0.99 1.00 0.97 1.01 0.96 1.00 0.99 1.01 0.98 Heavy nuclide 0.97 0.98 1.00 1.06 1.00 1.09 0.98 0.98 0.98 1.00 Neutron Total 0.95 0.93 1.17 1.27 1.19 1.35 0.95 1.06 0.99 1.12 Emission Spontaneous fission 0.95 0.93 1.18 1.30 1.21 1.38 0.93 1.07 0.97 1.13 (n/s) Alpha-n 1.14 1.07 1.15 1.04 0.98 0.95 1.03 0.97 Gamma Total 1.00 0.99 1.00 0.99 0.99 0.98 0.99 0.98 0.99 0.97 emission Fission product 0.95 0.93 0.97 0.93 0.97 0.91 0.95 0.92 0.96 0.91 (γ/s) Heavy nuclide 1.19 1.20 1.22 1.29 1.22 1.32 1.20 1.20 1.20 1.21 Gamma Total 0.57 0.57 0.56 0.56 0.56 0.55 0.56 0.56 0.56 0.56 emission Fission product 0.55 0.55 0.55 0.54 0.55 0.54 0.55 0.55 0.55 0.54 (MeV/s) Heavy nuclide 1.03 1.04 1.06 1.12 1.06 1.15 1.05 1.04 1.04 1.05
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 80 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 54: The ratio of SCALE to WIMS predictions at the maximum cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 H3 1.10 1.05 1.09 1.06 1.10 1.06 1.10 1.07 1.11 1.06 Br84 Kr83M Kr85 0.91 0.89 0.93 0.92 0.94 0.91 0.92 0.91 0.93 0.90 Kr85M Kr87 Kr88 Kr89 Rb86 Rb88 Rb89 Rb90 Rb91 Sr89 Sr90 0.93 0.91 0.94 0.93 0.95 0.93 0.97 0.97 0.98 0.97 Sr91 Sr92 Y90 0.96 0.94 0.97 0.96 0.98 0.96 1.01 1.00 1.02 1.00 Y92 Y93 Y94 Zr95 Zr97 Nb94 1.30 0.97 1.04 0.80 1.10 0.78 0.61 0.33 0.63 0.29 Nb95 Nb97 Nb97M Mo101 Tc104 Ru103 Ru105 Ru106 Rh106 Ag108M 2.12 3.72 12.02 60.05 13.25 137.65 Ag110M Sn127 Sb124 Sb125 0.80 0.57 0.89 0.52 Sb128 Sb128M Sb129 Sb130M Sb131 Te131 Te132 Te133 Te134 I127 1.03 1.02 1.08 1.05 1.06 1.03 1.02 0.99 1.00 0.94 I129 1.03 1.06 1.02 1.03 1.01 1.03 1.04 1.03 1.02 1.00 I130 I131 I132 I133 I134 I135 I136 Xe131M Xe133 Xe133M Xe135 Xe135M Xe137
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 81 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Xe138 Cs133 Cs134 0.91 0.87 0.91 0.82 Cs135 1.02 1.04 1.04 1.06 1.03 1.06 1.01 1.02 1.01 1.03 Cs136 Cs137 1.02 1.03 1.03 1.03 1.03 1.03 1.02 1.03 1.03 1.03 Cs138 Cs139 Cs140 Ba133 Ba137M 1.02 1.03 1.02 1.03 1.02 1.03 1.02 1.03 Ba139 Ba140 Ba141 La140 La141 La142 Ce143 Ce144 Pr144 Pr146 Pm147 1.01 1.00 1.01 1.03 Pm148 Pm148M Pm150 Pm154 Eu152 1.95 2.06 2.15 2.46 2.11 2.36 1.89 1.92 1.82 1.69 Eu154 0.94 0.59 0.98 0.59 1.06 0.49 0.89 0.67 0.98 0.62 Eu155 0.44 0.41 0.45 0.47 0.41 0.38 Eu156 Ta182 Hg203 U234 1.00 0.98 0.99 1.00 1.00 1.02 1.00 1.01 1.00 1.06 U235 1.00 0.99 0.99 0.90 1.00 0.79 0.99 0.97 0.99 0.92 U236 1.03 1.02 1.07 1.07 1.08 1.06 1.04 1.03 1.05 1.02 U238 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 Np239 1.10 1.47 1.30 1.26 1.18 Pu238 0.93 0.92 1.10 1.24 1.11 1.24 1.06 1.07 1.07 1.08 Pu239 0.99 1.00 0.98 0.87 0.99 0.85 0.98 0.97 0.98 0.96 Pu240 1.00 1.00 1.15 1.11 1.14 1.07 1.01 1.04 1.01 1.03 Pu241 0.94 0.97 1.06 1.00 1.12 0.97 0.96 0.98 0.98 0.96 Am241 0.96 0.98 1.08 1.01 1.14 0.98 0.97 0.99 0.99 0.97 Am243 1.15 1.11 1.78 1.47 1.89 1.30 1.24 1.25 1.30 1.18 Cm242 1.53 1.92 1.69 2.00 1.52 1.42 1.51 1.42 1.46 Cm243 0.84 1.43 1.18 1.54 1.06 0.95 1.03 1.00 1.00 Cm244 0.98 1.98 1.72 2.11 1.60 1.22 1.18 1.29 1.12 Total 0.99 0.98 1.02 1.04 1.03 1.04 1.01 1.01 1.02 1.03 Decay Heat Fission product 0.99 0.99 1.00 1.00 1.00 1.00 1.01 1.01 1.02 1.01 Heavy nuclide 0.98 0.98 1.06 1.06 1.07 1.08 0.98 1.01 0.99 1.04 Neutron Total 1.01 1.02 1.14 1.33 1.14 1.57 1.04 1.18 1.04 1.16 Emission Spontaneous fission 1.01 1.02 1.15 1.44 1.14 1.67 1.02 1.20 1.02 1.16 (n/s) Alpha-n 1.13 1.15 1.15 1.16 1.05 1.09 1.06 1.12 Gamma Total 2.17 1.63 2.21 1.88 2.30 1.89 2.31 1.97 2.41 1.95 emission Fission product 2.26 1.95 2.32 2.13 2.36 2.10 2.36 2.12 2.43 2.07 (γ/s) Heavy nuclide 0.85 0.79 0.87 0.84 0.92 0.85 0.79 0.81 0.82 0.88 Gamma Total 1.14 1.10 1.15 1.13 1.16 1.13 1.15 1.13 1.16 1.12 emission Fission product 1.13 1.11 1.15 1.13 1.16 1.13 1.15 1.13 1.16 1.12 (MeV/s) Heavy nuclide 0.88 0.86 0.95 0.90 0.99 0.89 0.85 0.87 0.87 0.88
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 82 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 55: Summary of the ratio SCALE to WIMS predictions over all cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 Min – Max 0.22 - 1.95 0.50 - 2.06 0.13 - 2.15 0.17 - 2.47 0.10 - 2.11 0.17 - 2.36 0.38 - 1.90 0.33 - 1.92 0.31 - 1.82 0.29 - 1.70 Fission Products31 Mean ; SD 1.04 ; 0.25 1.00 ; 0.27 1.03 ; 0.31 1.01 ; 0.38 1.03 ; 0.31 0.99 ; 0.37 0.99 ; 0.20 0.96 ; 0.23 0.99 ; 0.20 0.94 ; 0.22 Min – Max 0.82 - 1.15 0.84 - 1.54 0.98 - 1.99 0.87 - 1.73 0.99 - 2.11 0.79 - 1.60 0.84 - 1.42 0.92 - 1.51 0.86 - 1.43 0.92 - 1.47 Heavy Nuclides Mean ; SD 1.00 ; 0.06 1.02 ; 0.12 1.26 ; 0.35 1.18 ; 0.26 1.30 ; 0.39 1.11 ; 0.22 1.03 ; 0.11 1.05 ; 0.11 1.05 ; 0.12 1.03 ; 0.09 Min – Max 0.99 - 1.02 0.98 - 1.00 1.00 - 1.04 0.98 - 1.05 1.01 - 1.04 0.97 - 1.06 1.00 - 1.03 0.99 - 1.02 1.01 - 1.03 0.97 - 1.03 Decay Heat Mean ; SD 1.01 ; 0.01 0.99 ; 0.01 1.03 ; 0.01 1.04 ; 0.02 1.03 ; 0.01 1.04 ; 0.02 1.01 ; 0.01 1.01 ; 0.01 1.02 ; 0.01 0.99 ; 0.02 Neutron Emission Min – Max 0.95 - 1.01 0.92 - 1.02 1.14 - 1.17 1.27 - 1.74 1.14 - 1.19 1.35 - 1.64 0.95 - 1.05 1.06 - 1.21 0.99 - 1.04 1.12 - 1.17 (n/s) Mean ; SD 1.00 ; 0.02 1.00 ; 0.03 1.16 ; 0.01 1.56 ; 0.18 1.15 ; 0.02 1.57 ; 0.10 0.98 ; 0.04 1.11 ; 0.06 1.01 ; 0.02 1.14 ; 0.02 Gamma emission Min – Max 1.00 - 4.53 0.99 - 2.67 1.00 - 4.39 0.99 - 2.92 0.99 - 4.49 0.98 - 2.39 0.99 - 3.26 0.98 - 3.11 0.99 - 3.27 0.97 - 2.23 (γ/s) Mean ; SD 2.46 ; 0.78 1.84 ; 0.32 2.47 ; 0.74 2.01 ; 0.37 2.53 ; 0.75 1.89 ; 0.28 1.77 ; 0.63 1.77 ; 0.62 1.81 ; 0.64 1.63 ; 0.41 Gamma emission Min – Max 0.57 - 1.62 0.57 - 1.18 0.56 - 1.60 0.56 - 1.28 0.56 - 1.63 0.55 - 1.18 0.56 - 1.29 0.56 - 1.24 0.56 - 1.30 0.56 - 1.12 (MeV/s) Mean ; SD 1.16 ; 0.18 1.07 ; 0.11 1.17 ; 0.18 1.10 ; 0.13 1.18 ; 0.18 1.08 ; 0.12 1.07 ; 0.13 1.07 ; 0.13 1.07 ; 0.13 1.02 ; 0.11
31 The results for Ag108M have been omitted from these calculations, which demonstrates differences of up to a factor of 170. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 83 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 56: The ratio of SCALE to WIMS predictions of the gamma spectrum (γ/s) at shutdown.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 1 3.24 3.04 4.37 3.62 4.84 3.52 3.72 3.27 4.29 3.28 2 2.51 2.32 2.43 2.31 2.44 2.27 2.46 2.32 2.47 2.28 3 2.76 2.09 3.05 2.31 3.25 2.16 2.80 2.15 3.10 2.00 4 1.03 1.01 1.16 1.10 1.20 1.10 1.08 1.03 1.14 1.04 5 0.87 0.85 0.88 0.88 0.88 0.89 0.86 0.84 0.87 0.83 6 0.90 0.85 0.91 0.85 0.92 0.83 0.89 0.84 0.90 0.82 /s) γ 7 0.66 0.66 0.65 0.65 0.64 0.65 0.65 0.64 0.64 0.64 8 0.62 0.62 0.63 0.61 0.63 0.61 0.61 0.61 0.61 0.61 9 0.46 0.45 0.46 0.45 0.46 0.44 0.46 0.45 0.46 0.45 10 0.55 0.57 0.56 0.55 0.56 0.55 0.55 0.56 0.55 0.56 11 0.42 0.42 0.42 0.42 0.43 0.41 0.42 0.42 0.42 0.42 12 0.55 0.54 0.56 0.53 0.56 0.52 0.55 0.54 0.56 0.53
Total gamma emission ( 13 0.41 0.40 0.41 0.39 0.41 0.39 0.40 0.40 0.40 0.39 14 0.36 0.31 0.37 0.32 0.37 0.31 0.36 0.32 0.37 0.30 15 0.26 0.23 0.26 0.23 0.26 0.22 0.25 0.24 0.26 0.23 16 0.45 0.40 0.46 0.41 0.47 0.38 0.45 0.41 0.46 0.40 17 0.34 0.31 0.35 0.31 0.35 0.30 0.34 0.32 0.35 0.31 18 0.19 0.18 0.19 0.18 0.20 0.17 0.19 0.18 0.20 0.18 1 8.73 7.68 8.92 7.94 9.10 7.74 8.71 7.78 9.02 7.68 2 2.30 2.11 2.34 2.16 2.36 2.11 2.31 2.14 2.36 2.11 3 3.16 2.19 3.32 2.42 3.51 2.22 3.10 2.27 3.41 2.09 4 1.50 1.41 1.52 1.42 1.54 1.39 1.48 1.40 1.52 1.37 /s)
γ 5 0.83 0.77 0.85 0.78 0.87 0.76 0.82 0.76 0.84 0.74 6 0.87 0.82 0.89 0.83 0.90 0.81 0.86 0.81 0.88 0.80 7 0.61 0.61 0.62 0.60 0.62 0.60 0.61 0.60 0.61 0.59 8 0.62 0.62 0.63 0.61 0.63 0.61 0.61 0.61 0.61 0.61 9 0.46 0.45 0.46 0.44 0.46 0.44 0.46 0.45 0.46 0.44 10 0.55 0.57 0.56 0.55 0.56 0.55 0.55 0.56 0.55 0.56 11 0.42 0.42 0.42 0.42 0.43 0.41 0.42 0.42 0.42 0.42 12 0.55 0.54 0.56 0.53 0.56 0.52 0.55 0.54 0.56 0.53 13 0.41 0.40 0.41 0.39 0.41 0.39 0.40 0.40 0.40 0.39 14 0.36 0.31 0.37 0.32 0.37 0.31 0.36 0.32 0.37 0.30 Fission gamma emission product ( 15 0.26 0.23 0.26 0.23 0.26 0.22 0.25 0.24 0.26 0.23 16 0.45 0.40 0.46 0.41 0.47 0.38 0.45 0.41 0.46 0.40 17 0.34 0.31 0.35 0.31 0.35 0.30 0.34 0.32 0.35 0.31 18 0.19 0.18 0.19 0.18 0.20 0.17 0.19 0.18 0.20 0.18 1 1.64 1.66 1.69 1.77 1.68 1.82 1.66 1.65 1.65 1.66 2 1.03E+2 91.36 86.10 73.44 82.80 64.79 84.12 64.47 79.08 47.63
/s) 3 1.75 1.75 1.78 1.86 1.77 1.90 1.75 1.72 1.74 1.69 γ 4 0.86 0.87 0.89 0.94 0.88 0.96 0.87 0.87 0.87 0.89 5 0.89 0.89 0.91 0.95 0.90 0.97 0.89 0.89 0.89 0.89 6 10.11 9.70 9.31 8.80 9.26 8.28 8.31 7.30 8.41 6.19 7 0.87 0.88 0.90 0.95 0.89 0.97 0.88 0.88 0.88 0.88 8 1.22 1.23 1.22 1.27 1.22 1.29 1.23 1.22 1.23 1.19 9 1.01 0.89 0.97 1.05 0.97 1.09 1.10 0.94 1.09 0.89 10 6.29E-5 2.41E-4 1.10E-5 5.79E-5 1.68E-5 1.75E-4 7.91E-7 6.30E-6 1.36E-6 5.94E-5 11 2.72E-3 2.56E-3 4.59E-4 2.37E-4 7.14E-4 2.21E-4 3.20E-5 3.11E-5 5.66E-5 6.11E-5
Heavy nuclide gamma emission ( 12 1.52E+4 1.25E+5 2.88E+4 3.55E+5 8.53E+3 3.07E+5 1.89E+5 3.72E+6 3.13E+4 3.90E+6 13 1.26 1.63 0.75 1.57 0.43 1.02 1.11 5.28 0.57 2.91 14 1.01E+6 8.34E+6 1.93E+6 2.38E+7 5.68E+5 2.05E+7 1.25E+7 2.49E+8 2.06E+6 2.61E+8
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 84 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 57: The ratio of SCALE to WIMS predictions of the gamma spectrum (γ/s) at the maximum cooling times.
Fuel type Magnox AGR PWR Enrichment (%) 0.711 2.67 4 2.5 5 Irradiation (MWd/t) 1000 10000 5000 25000 5000 45000 5000 25000 5000 65000 1 12.59 2.71 11.87 4.52 17.60 4.86 19.59 7.27 31.08 7.38 2 3.81 2.87 3.89 3.32 4.02 3.31 4.04 3.44 4.22 3.39 3 7.35 1.67 5.53 2.29 9.39 2.47 9.91 3.20 24.14 3.56 4 5.84E+2 53.99 1.05E+3 72.95 1.29E+3 36.49 1.49E+3 1.41E+2 1.79E+3 56.76 /s) γ 5 9.07E+2 39.08 9.30E+2 54.10 1.42E+3 28.27 1.77E+2 19.99 2.85E+2 10.92 6 1.36E+3 3.29E+3 2.04E+3 4.78E+3 1.37E+3 3.33E+3 5.37E+3 2.40E+3 3.29E+3 1.27E+3 7 2.28E+3 89.95 2.61E+3 1.17E+2 3.20E+3 56.66 9.83E+2 87.23 1.56E+3 41.14 8 1.05 1.06 1.07 1.07 1.07 1.07 1.06 1.06 1.07 1.06 9 1.21E+2 13.82 1.13E+2 15.62 1.48E+2 10.61 7.35 1.42 11.65 1.05 10 2.38 2.25 2.42 2.32 2.44 2.27 2.35 1.58 2.43 1.31
Total gamma emission ( 11 51.07 2.96E+2 2.65E+2 8.37E+2 2.75E+2 1.01E+3 6.40E+2 2.41E+2 7.67E+2 1.43E+2 12 9.08 78.61 9.42 57.49 6.11 94.55 1.40E+2 1.08E+3 64.68 3.95E+3 13 0.65 0.62 0.27 0.26 0.25 0.28 0.41 0.47 0.42 0.59 14 76.48 2.11E+3 56.92 1.28E+3 23.15 3.39E+3 3.17E+2 2.69E+4 72.23 2.03E+5 1 47.69 35.60 49.57 42.13 51.08 41.23 51.21 41.26 53.82 39.23 2 3.86 3.15 3.98 3.54 4.07 3.49 4.08 3.57 4.24 3.48 /s)
γ 3 1.27E+4 1.21E+3 9.25E+3 1.34E+3 1.21E+4 9.09E+2 5.46E+2 68.04 8.54E+2 39.09 4 3.46E+3 1.15E+3 3.94E+3 1.90E+3 4.51E+3 1.70E+3 2.75E+3 1.49E+3 2.80E+3 1.00E+3 5 6.91E+3 4.56E+2 4.09E+3 4.91E+2 5.54E+3 3.28E+2 1.91E+2 23.57 3.02E+2 13.76 6 6.72E+5 4.44E+4 4.73E+5 5.06E+4 6.32E+5 2.71E+4 2.77E+4 3.32E+3 4.48E+4 1.88E+3 7 1.83E+4 2.09E+3 1.42E+4 2.54E+3 1.71E+4 1.75E+3 1.15E+3 1.36E+2 1.86E+3 77.90 8 1.05 1.06 1.07 1.07 1.07 1.07 1.06 1.06 1.07 1.06 9 1.86E+2 14.17 1.20E+2 15.74 1.60E+2 10.67 7.36 1.42 11.67 1.05 10 2.39 2.25 2.42 2.32 2.44 2.27 2.35 1.58 2.43 1.31 11 9.13E+4 5.18E+3 5.11E+4 5.64E+3 7.14E+4 3.74E+3 2.33E+3 2.64E+2 3.87E+3 1.51E+2 12 4.07E+14 9.40E+13 6.31E+14 1.77E+14 8.59E+14 1.44E+14 1.16E+9 6.09E+8 1.66E+9 8.62E+8 Fission gamma emission product ( 13 1.81E+14 2.58E+14 2.16E+14 1.88E+14 2.67E+14 2.59E+14 2.65 2.56 2.67 2.56 14 6.14E+14 8.70E+14 7.30E+14 6.39E+14 9.03E+14 8.78E+14 3.41 3.14 3.59 3.24 1 0.74 0.60 0.68 0.66 0.73 0.72 0.61 0.62 0.67 0.78 2 0.97 0.88 0.98 0.91 1.04 0.88 0.87 0.89 0.91 0.87
/s) 3 1.03 1.04 1.15 1.08 1.21 1.04 1.03 1.06 1.06 1.03 γ 4 1.67 0.96 1.51 1.20 1.45 1.05 1.32 1.04 1.29 0.94 5 1.76 1.01 1.18 1.25 1.26 1.13 0.94 1.07 1.05 1.02 6 2.36 1.98 1.40 1.74 1.26 1.66 1.36 1.17 1.20 1.01 7 3.66 0.94 1.65 1.21 1.66 1.08 1.38 1.03 1.43 0.97 8 3.08 1.24 2.03 1.11 2.22 0.97 1.62 0.99 1.83 0.94 9 1.24 1.19 1.24 1.29 1.24 1.21 1.23 1.23 1.23 1.38 10 1.42 1.54 1.41 1.42 1.40 1.44 1.42 1.77 1.41 2.93 11 0.95 0.94 0.95 0.89 0.96 0.76 0.94 0.80 0.94 0.50
Heavy nuclide gamma emission ( 12 1.74 32.43 1.44 19.91 0.93 51.39 5.42 4.04E+2 1.69 3.05E+3 13 0.65 0.62 0.27 0.26 0.25 0.28 0.41 0.47 0.42 0.59 14 76.48 2.11E+3 56.92 1.28E+3 23.15 3.39E+3 3.17E+2 2.69E+4 72.23 2.03E+5
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 85 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 58: Overall results for the heavy nuclides.
Nuclide Magnox AGR PWR (Obrigheim) PWR (Calvert Cliffs) PWR (Goesgen) PWR32 U234 0.86 ; 0.05 0.94 ; 0.17 0.99 ; 0.15 1.34 ; 0.12 1.10 ; 0.22 U235 1.01 ; 0.03 1.06 ; 0.05 1.05 ; 0.10 1.05 ; 0.03 1.24 ; 0.17 1.07 ; 0.11 U236 0.95 ; 0.05 0.92 ; 0.09 0.95 ; 0.05 0.98 ; 0.02 0.99 ; 0.01 0.96 ; 0.04 U238 1.00004 ; 0.00006 1.000 ; 0.001 1.000 ; 0.001 0.99 ; 0.01 0.996 ; 0.001 0.997 ; 0.004 Np237 1.02 ; 0.09 0.78 ; 0.07 0.96 ; 0.14 Pu238 0.70 ; 0.14 0.86 ; 0.09 1.00 ; 0.14 0.92 ; 0.05 0.94 ; 0.07 0.97 ; 0.12 Pu239 1.15 ; 0.04 1.04 ; 0.04 1.10 ; 0.05 1.09 ; 0.02 1.11 ; 0.06 1.10 ; 0.04 Pu240 0.93 ; 0.05 1.01 ; 0.06 1.01 ; 0.06 0.99 ; 0.01 0.96 ; 0.02 1.00 ; 0.05 Pu241 0.89 ; 0.09 1.08 ; 0.15 1.08 ; 0.09 1.02 ; 0.02 1.09 ; 0.04 1.07 ; 0.07 Pu242 0.73 ; 0.07 0.93 ; 0.08 0.95 ; 0.16 0.89 ; 0.02 0.87 ; 0.06 0.93 ; 0.13 Pu244 0.60 ; 0.11 0.60 ; 0.11 Am241 0.90 ; 0.11 1.03 ; 0.15 1.33 ; 0.46 0.94 ; 0.11 1.20 ; 0.10 1.14 ; 0.34 Am242m 0.60 ; 0.20 1.10 ; 0.23 0.71 ; 0.29 Am243 0.82 ; 0.31 1.04 ; 0.28 0.95 ; 0.11 1.01 ; 0.23 Cm242 0.64 ; 0.12 0.93 ; 0.07 0.93 ; 0.09 0.95 ; 0.04 0.93 ; 0.09 Cm243 2.11 ; 1.35 2.11 ; 1.35 Cm244 0.53 ; 0.19 0.82 ; 0.11 0.90 ; 0.16 0.84 ; 0.04 0.76 ; 0.15 0.86 ; 0.14 Cm245 0.74 ; 0.19 0.74 ; 0.19 Cm246 0.62 ; 0.01 0.62 ; 0.01 Pu 1.06 ; 0.02 1.02 ; 0.04 1.07 ; 0.05 1.04 ; 0.01 1.04 ; 0.03 1.06 ; 0.04
32 Mean and standard deviation calculated using all PWR sample results. IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 86 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Table 59: Overall results for the activation and fission products.
Nuclide Magnox AGR PWR (Obrigheim) PWR (Calvert Cliffs) PWR (Goesgen) PWR C14 0.96 ; 0.28 0.96 ; 0.28 Se79 5.51 ; 0.54 5.51 ; 0.54 Sr90 1.01 ; 0.01 0.96 ; 0.12 1.00 ; 0.07 Zr95 0.82 ; 0.11 Nb95 2.13 ; 0.35 1.52 ; 0.01 Mo95 0.95 ; 0.05 0.95 ; 0.05 Tc99 1.19 ; 0.20 1.05 ; 0.15 1.15 ; 0.19 Ru101 0.96 ; 0.08 0.96 ; 0.08 Ru106 0.80 ; 0.25 0.80 ; 0.25 Rh103 1.11 ; 0.10 1.11 ; 0.10 Ag109 1.45 ; 0.67 1.45 ; 0.67 Sn126 4.77 ; 0.71 4.77 ; 0.71 Sb125 2.06 ; 0.19 2.90 ; 0.09 2.90 ; 0.09 I129 0.85 ; 0.31 1.00 ; 0.04 0.88 ; 0.27 Cs133 0.98 ; 0.04 0.98 ; 0.04 Cs134 1.10 ; 0.23 1.16 ; 0.03 1.08 ; 0.05 1.06 ; 0.10 1.08 ; 0.06 Cs135 1.03 ; 0.02 1.06 ; 0.05 1.04 ; 0.04 Cs137 1.09 ; 0.10 1.00 ; 0.03 1.01 ; 0.03 0.98 ; 0.01 1.00 ; 0.05 1.00 ; 0.03 Ce144 0.95 ; 0.13 1.12 ; 0.07 1.06 ; 0.01 1.06 ; 0.01 Pr144 0.96 ; 0.09 Nd142 0.82 ; 0.10 0.82 ; 0.30 0.99 ; 0.08 0.99 ; 0.08 Nd143 1.02 ; 0.01 1.04 ; 0.04 1.07 ; 0.07 1.07 ; 0.07 Nd144 0.99 ; 0.02 0.96 ; 0.01 0.95 ; 0.02 0.95 ; 0.02 Nd145 1.01 ; 0.03 1.00 ; 0.01 1.01 ; 0.02 1.01 ; 0.02 Nd146 0.986 ; 0.005 0.98 ; 0.01 0.979 ; 0.005 0.979 ; 0.005 Nd148 0.998 ; 0.001 1.0000 ; 0.0001 0.9999 ; 0.0002 1.001 ; 0.002 1.000 ; 0.001 Nd150 0.98 ; 0.01 0.98 ; 0.01 0.97 ; 0.03 0.97 ; 0.03 Pm147 1.05 ; 0.25 1.05 ; 0.25 Sm147 0.97 ; 0.06 0.97 ; 0.06 Sm148 0.95 ; 0.08 0.95 ; 0.08 Sm149 1.17 ; 0.17 1.17 ; 0.17 Sm150 1.03 ; 0.03 1.03 ; 0.03 Sm151 1.35 ; 0.05 1.35 ; 0.05 Sm152 1.22 ; 0.07 1.22 ; 0.07 Sm154 1.07 ; 0.07 1.07 ; 0.07 Eu151 0.71 ; 0.15 0.71 ; 0.15 Eu153 1.09 ; 0.05 1.09 ; 0.05 Eu154 1.89 ; 0.17 1.49 ; 0.14 1.77 ; 0.33 1.55 ; 0.21 Eu155 0.63 ; 0.10 1.05 ; 0.09 1.05 ; 0.09 Gd155 1.04 ; 0.24 1.04 ; 0.24
Table 60: Overall results for decay heat and neutron emission.
Decay heat (PWR) 1.03 ; 0.03 Neutron emission (AGR) 0.80 ; 0.03
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 87 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Appendix C: Figures.
1.50 Magnox 1.40 AGR Obrigheim 1.30 Calvert Cliffs Goesgen 1.20
1.10
1.00
Calculation / Experiment (U235) Experiment / Calculation 0.90
0.80
0.70 0 10000 20000 30000 40000 50000 60000 Irradiation (MWd/t)
Figure 1: Calculation over experiment for U235 as a function of irradiation.
1.50 Magnox 1.40 AGR Obrigheim 1.30 Calvert Cliffs Goesgen 1.20
1.10
1.00
Calculation / Experiment (U235) Experiment / Calculation 0.90
0.80
0.70 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 U235 depletion (fraction)
Figure 2: Calculation over experiment for U235 as a function of U235 depletion.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 88 of 115 RAT 1972 Issue 02 RAWG/P(01)04
1.25
1.20
1.15
1.10
1.05
Magnox 1.00 AGR
Calculation / Experiment (Pu239) Experiment / Calculation Obrigheim 0.95 Calvert Cliffs Goesgen
0.90 0 10000 20000 30000 40000 50000 60000 Irradiation (MWd/t)
Figure 3: Calculation over experiment for Pu239 as a function of irradiation.
1.20
Magnox 1.15 AGR Obrigheim Calvert Cliffs 1.10 Goesgen
1.05
1.00 Calculation / Experiment (Pu) Experiment / Calculation
0.95
0.90 0 10000 20000 30000 40000 50000 60000 Irradiation (MWd/t)
Figure 4: Calculation over experiment for plutonium as a function of irradiation.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 89 of 115 RAT 1972 Issue 02 RAWG/P(01)04
1.40
Magnox
1.20 AGR Obrigheim Calvert Cliffs 1.00 Goesgen
0.80
0.60 Calculation / Experiment (Cm244) Experiment / Calculation 0.40
0.20 0 10000 20000 30000 40000 50000 60000 Irradiation (MWd/t)
Figure 5: Calculation over experiment for Cm244 as a function of irradiation.
2.40
AGR 2.20 Obrigheim Goesgen
2.00
1.80
1.60 Calculation / Experiment (Eu154) Experiment / Calculation
1.40
1.20 0 10000 20000 30000 40000 50000 60000 Irradiation (MWd/t)
Figure 6: Calculation over experiment for Eu154 as a function of irradiation.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 90 of 115 RAT 1972 Issue 02 RAWG/P(01)04
1.8
1.6 Tobias Fit (1989) JEF-1 Calculation 1.4 JEF-2.2 Calculation
1.2
1.0
0.8
0.6
0.4
Heat rate per fissionx time (MeV/s0.2/ fission . s)
0.0 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 7: The decay heat from fission products following a U235 fission pulse compared to the results of Tobias.
1.3
1.2 Tobias Fit (1989)
1.1 JEF-1 Calculation JEF-2.2 Calculation 1.0
0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2 Heat rate per fission x time (MeV/s / fission . s) . fission / (MeV/s time x fission per rate Heat 0.1
0.0 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 8: The decay heat from fission products following a Pu239 fission pulse compared to the results of Tobias.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 91 of 115 RAT 1972 Issue 02 RAWG/P(01)04
1.3
1.2 Dickens (1981) 1.1 JEF-1 Calculation
1.0 JEF-2.2 Calculation
0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2
Heat rate per fission x time (MeV/s / fission . s) x (MeV/s time / fission fission per rate Heat 0.1
0.0 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 9: The decay heat from fission products following a Pu239 fission pulse compared to the results of Dickens.
1.8
Dickens (1981) 1.6 JEF-1 Calculation
1.4 JEF-2.2 Calculation
1.2
1.0
0.8
0.6
0.4
Heat rate per fis s0.2 ion tim x e (MeV/s fis / s ion . s )
0.0 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06
Tim e (s)
Figure 10: The decay heat from fission products following a Pu241 fission pulse compared to the results of Dickens.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 92 of 115 RAT 1972 Issue 02 RAWG/P(01)04
2.4
2.2 Akiyama measurements (1985)
2.0 JEF-1 Calculation JEF-2.2 Calculation 1.8
1.6
1.4
1.2
1.0
0.8
0.6
0.4 Heat rate per fissionx time (MeV/s/ fission . s) 0.2
0.0 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 11: The decay heat from fission products following a U238 fission pulse compared to the results of Akiyama.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 93 of 115 RAT 1972 Issue 02 RAWG/P(01)04
1.25
1.20
1.15
1.10
1.05
1.00
0.95
Calculation / Experiment / Calculation 0.90
0.85
0.80
0.75 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 12: The fission product decay heat following a U235 fission pulse calculated using JEF-2.2 compared to the results of Tobias.
1.25
1.20
1.15
1.10
1.05
1.00
0.95
Calculation / Experiment / Calculation 0.90
0.85
0.80
0.75 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Time (s)
Figure 13: The fission product decay heat following a Pu239 fission pulse calculated using JEF-2.2 compared to the results of Tobias.
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 94 of 115 RAT 1972 Issue 02 RAWG/P(01)04
Appendix D: WIMS Input Examples
Magnox: Hunterston A
********************************************************************* * * Station : Hunterston_A_25 * Fuel type : U * Final Irradiation (MWd/t) : 12000 * Rating (MW/t) : 1.5335 * Initial U235 enrichment (%wt) : natural * **********************************************************************
NCYCLE 1 82
XHEAD 1 2 nmat 7 nregion 7 nmesh 27 endp
* Fuel material 1 18.49 620. 1 U234 5.40785E-3 U235 7.10970E-1 U238 9.92836E1
* Magnox (AL80) cladding. Smeared into gap material 2 1.7428 559 2 Mg 99.2 Al 0.8
* Magnox (AL80) fins. Smeared material 3 0.54791 559 2 Mg 99.2 Al 0.8
* Splitters, braces, and coolant at 1.1514MPa material 4 0.18941 551 3 C 1.721 O 4.583 Mg 9.295E+1 Al 7.496E-1
* Graphite sleeve smeared into sleeve-channel gap material 5 1.4640 530 3 C 100
* Graphite core material 6 2.0470 530 3 C 100
* Graphite holes material 7 1.5272 530 3 C 100
* Define the fuel annuli annulus 1 1.4713 1 * Fuel annulus 2 1.689 2 * Magnox cladding annulus 3 2.731 3 * Magnox cladding fins annulus 4 5.08 4 * Coolant and splitters annulus 5 6.699 5 * Graphite sleeve annulus 6 11.32 6 * Graphite core annulus 7 11.82 7 * Graphite core holes mesh 101113101 burn all begin
WPRES 2 3
***************************************************** * Begin the resonance treatment WPRES - WTHES - WRES ***************************************************** nuclide U238 620. nuclide U235 620. begin
WTHES 3 begin
WRES 3 4 nuclide U238 620. nuclide U235 620. begin
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 95 of 115 RAT 1972 Issue 02 RAWG/P(01)04
WTHES 4
***************************************************** * Perform the flux calculation ***************************************************** begin
WPIP 4 begin
WEDIT 4
***************************************************** * WEDIT : output the masses of the actinides ***************************************************** materials 1 nuclides actinides masses norm 1.5335E+06 power reactions fission power rates begin
WINTER 4 15 0 1
***************************************************** * WINTER - copy interface 4 for TRAIL input ***************************************************** copy begin print 1 WBRNUP 4 1
******************************************************************* * WBRNUP - Perform burnup calculation and change number densities ******************************************************************* rating 1 1.5335 qual11-5 steps 1 0.652103 qual16-8 steps 1 3.260515 qual 1 9 -12 steps 4 3.260515 qual 1 13 -31 steps 10 6.521030 qual 1 32 -82 steps 20 6.521030 trigger 1 alpha Pu240 620. radius 1.4713 fuel 1 alpha Pu242 620. radius 1.4713 fuel 1 begin print 0 finish stop
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 96 of 115 RAT 1972 Issue 02 RAWG/P(01)04
AGR: Hinkley Point B
******************************************************************* * WIMS case created by WICID 6.2. * * Station : Hinkley_B_32 * Final Irradiation (MWd/t) : 30000.00000 * Rating (MW/t) : 12.83000 * Initial U235 enrichment (%wt) : 2.17000 * Fuel Design : STAGE_2 * * Modifications * graphite sleeve material * TRIGGER codeword used * burnup steps * radius of outer annulus in PIJ *******************************************************************
NCYCLE 1 17
XHEAD 1 2
******************************************************************* * HEAD - Define geometry and calculate macroscopic cross sections. *******************************************************************
NMATERIALS 10 NREGIONS 18 3 NMESHES 18 NRODS 36331 ENDPREL
* UO2 Fuel regions MATERIAL 1 10.7600 900.00 1 U234 1.8694E-02 U235 1.9129E+00 U236 2.5565E-02 U238 8.6196E+01 O 1.1846E+01 MATERIAL2=1 MATERIAL3=1 * Cladding (20/25 Nb Stainless Steel) MATERIAL 4 7.9800 805.00 2 FE 53.92 CR 20.0 NI 25.0 NB 1.0 C 0.08 * Tie Bar (Nimonic Alloy) * Note that the tie bar is in the coolant resonance region MATERIAL 5 8.0200 740.65 3 NI 43.50 CR 16.50 MO 3.30 AL 1.20 TI 1.20 C 0.06 ZR 0.025 CU 0.50 B 0.0035 CO 0.25 MN 0.20 NB 0.10 SI 0.20 N 0.015 P 0.015 FE 32.9165 S32 0.0142119 S34 0.0006690 S33 0.0001157 S36 0.0000034 * Graphite bulk moderator MATERIAL 6 1.7501 713.15 4 C 100.00 * CO2 coolant in central fuel channel MATERIAL 7 0.0300 740.65 3 C 27.303 O 72.697 * CO2 coolant between and around graphite sleeve * Note that these are defined in the moderator resonance region MATERIAL 8 0.0313 713.15 4 C 27.303 O 72.697 * Fission gas plenum * In reality the plenum contains He which is not in WIMS libraries * Note that the pin centre is defined in the fuel resonance region MATERIAL 9 0.00001 900.00 1 C 27.303 O 72.697 * Graphite sleeve MATERIAL 10 1.7424 713.15 4 C 100.00
ANNULUS 1 0.5061 5 ANNULUS 2 1.1557 7 ANNULUS 3 3.7719 7 ANNULUS 4 6.4389 7 ANNULUS 5 9.1567 7 ANNULUS 6 9.5900 7 ANNULUS 7 11.9060 10 ANNULUS 8 13.1760 8 ANNULUS 9 25.1593 6 ARRAY 1 1 6 2.4638 0.0 ARRAY 2 1 12 5.0800 0.0 ARRAY 3 1 18 7.7978 0.0 RODSUB 1 1 0.3175 9 RODSUB 1 2 0.7258 1 RODSUB 1 3 0.7655 4 RODSUB 2 1 0.3175 9 RODSUB 2 2 0.7258 2 RODSUB 2 3 0.7655 4 RODSUB 3 1 0.3175 9 RODSUB 3 2 0.7258 3
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 97 of 115 RAT 1972 Issue 02 RAWG/P(01)04
RODSUB 3 3 0.7655 4
BURN ALL BEGIN
WPRES 2 4
******************************************************************* * PRES - Calculate subgroup cross sections for resonance treatment. *******************************************************************
NUCLIDE U235 900.00 NUCLIDE U238 900.00 BEGIN
WPIJ 4
******************************************************************* * PIJ - Calculate subgroup collision probabilities using a * simplified circular geometry for enhanced symmetry. *******************************************************************
NREGIONS 18 NANNULI 9 1 NRODS 36331 NTRACK 100 3 NSYMMETRY -12 ENDPREL
ANNULUS 1 0.5061 5 ANNULUS 2 1.1557 7 ANNULUS 3 3.7719 7 ANNULUS 4 6.4389 7 ANNULUS 5 9.1567 7 ANNULUS 6 9.5900 7 ANNULUS 7 11.9060 10 ANNULUS 8 13.1760 8 ANNULUS 9 25.1593 6
* Number of equispaced lines in each annulus
LINES2210101022210
ARRAY 1 1 6 2.4638 0.0 ARRAY 2 1 12 5.0800 0.0 ARRAY 3 1 18 7.7978 0.0 RODSUB 1 1 0.3175 9 RODSUB 1 2 0.7258 1 RODSUB 1 3 0.7655 4 RODSUB 2 1 0.3175 9 RODSUB 2 2 0.7258 2 RODSUB 2 3 0.7655 4 RODSUB 3 1 0.3175 9 RODSUB 3 2 0.7258 3 RODSUB 3 3 0.7655 4
BEGIN
WRES 4 3
******************************************************************* * RES - Calculate subgroup fluxes and macroscopic resonance * cross sections. *******************************************************************
NUCLIDE U235 900.00 NUCLIDE U238 900.00 BEGIN
WPIJ 3
******************************************************************* * PIJ - Main transport calculation. * Calculate collision probabilities using full geometry and * neutron energy group spectrum. * Use square outer boundary and include CO2 corner pins. *******************************************************************
NREGIONS 29 NANNULI 19 1 NRODS 40431 NTRACK 100 5 NSYMMETRY -4
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 98 of 115 RAT 1972 Issue 02 RAWG/P(01)04
ENDPREL
ANNULUS 1 0.5061 5 ANNULUS 2 1.1557 7 ANNULUS 3 3.7719 7 ANNULUS 4 6.4389 7 ANNULUS 5 9.1567 7 ANNULUS 6 9.5900 7 ANNULUS 7 11.9060 10 ANNULUS 8 13.1760 8 ANNULUS 9 14.4619 6 ANNULUS 10 15.6424 6 ANNULUS 11 16.7399 6 ANNULUS 12 17.7698 6 ANNULUS 13 18.7431 6 ANNULUS 14 19.6683 6 ANNULUS 15 20.5519 6 ANNULUS 16 21.3991 6 ANNULUS 17 22.2140 6 ANNULUS 18 23.0000 6 SQUARE 19 23.0000 6
* Number of equispaced lines in each annulus
LINES2210101022222222222225
ARRAY 1 1 6 2.4638 0.0 ARRAY 2 1 12 5.0800 0.0 ARRAY 3 1 18 7.7978 0.0 ARRAY 4 1 4 32.5269 0.0 RODSUB 1 1 0.3175 9 RODSUB 1 2 0.7258 1 RODSUB 1 3 0.7655 4 RODSUB 2 1 0.3175 9 RODSUB 2 2 0.7258 2 RODSUB 2 3 0.7655 4 RODSUB 3 1 0.3175 9 RODSUB 3 2 0.7258 3 RODSUB 3 3 0.7655 4 RODSUB 4 1 6.3683 8
REFLECT 2 TRUNCATE 8.0 QUAL 1 1 PLOT BEGIN
WPIP 3
******************************************************************* * PIP - Solve collision probability equations to calculate the * neutron flux in 172 energy groups. *******************************************************************
TOLERANCE 1E-06 BEGIN
WEDIT 3
******************************************************************* * EDIT - Print masses of actinides and reaction rates. *******************************************************************
MATERIALS123 NUCLIDES ACTINIDES MASSES NORM 1.283000E+07 POWER REACTIONS FISSION POWER RATES BEGIN
WINTER 3 30 0 1
******************************************************************* * INTER - Copy interfaces for TRAIL input. *******************************************************************
COPY BEGIN
PRINT 1 WBRNUP 3 1
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 99 of 115 RAT 1972 Issue 02 RAWG/P(01)04
******************************************************************* * BRNUP - Perform burnup calculation. *******************************************************************
ENDPREL
ALPHA PU240 900.00 COOLANT 7 FUEL123
ALPHA PU242 900.00 COOLANT 7 FUEL123
RATING 1 12.83000
QUAL 1 1 -4 STEPS 1 0.500000 QUAL 1 5 STEPS 2 6.794232 QUAL 1 6 STEPS 3 7.794232 QUAL 1 7 STEPS 5 7.794232 QUAL 1 8 STEPS 5 15.588465 QUAL 1 9 -12 STEPS 10 15.588465 QUAL 1 13 -17 STEPS 10 38.971161
TRIGGER 2
BEGIN
PRINT 0 FINISH STOP
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 100 of 115 RAT 1972 Issue 02 RAWG/P(01)04
PWR: Obrigheim – Assembly BE124, Pin G7
******************************************************************* * WIMS case created by WICID 6.0. * * Station : Obrigheim_12 * Pin Map : BE124 * Fuel type : UOX * Final Irradiation (MWd/t) : 40000.00000 * Rating (MW/t) : 29.00000 * Initial U235 enrichment (%wt) : 3.00000 * Modifications: * first condense energy changed from 820000 to 821000 * guide tube material changed to stainless steel * burnup steps * TRIGGER codeword used * ALPHA fuel material number *******************************************************************
NCYCLE 1 19
WHEAD 1 2
******************************************************************* * WHEAD - Define geometry and calculate macroscopic cross sections ******************************************************************* nmaterials 19 nxmesh 16 nymesh 16 nslab 1 nrods 0 6 3 1 endpre
* Water gap - Boron content (ppm) 500.00 material 1 0.72783 571.15 3 H 1.1189E+01 O 8.8761E+01 B 5.0000E-02
* Pin type 1, 3.0000 initial U235 %wt, fuel/clad/coolant material 2 10.4100 900.00 1 U234 2.3440E-02 U235 2.6446E+00 U236 1.3223E-02 U238 8.5471E+01 O 1.1847E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 3 5.6109 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 4 = 1
* Pin type 2, 3.0000 initial U235 %wt, fuel/clad/coolant material 5 10.4100 900.00 1 U234 2.3440E-02 U235 2.6446E+00 U236 1.3223E-02 U238 8.5471E+01 O 1.1847E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 6 5.6109 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 7 = 1
* Pin type 3, 3.0000 initial U235 %wt, fuel/clad/coolant material 8 10.4100 900.00 1 U234 2.3440E-02 U235 2.6446E+00 U236 1.3223E-02 U238 8.5471E+01 O 1.1847E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 9 5.6109 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 10 = 1
* Pin type 4, 3.0000 initial U235 %wt, fuel/clad/coolant material 11 10.4100 900.00 1 U234 2.3440E-02 U235 2.6446E+00 U236 1.3223E-02 U238 8.5471E+01 O 1.1847E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 12 5.6109 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 13 = 1
* Pin type 5, 3.0000 initial U235 %wt, fuel/clad/coolant material 14 10.4100 900.00 1
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 101 of 115 RAT 1972 Issue 02 RAWG/P(01)04
U234 2.3440E-02 U235 2.6446E+00 U236 1.3223E-02 U238 8.5471E+01 O 1.1847E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 15 5.6109 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 16 = 1
* Guide tube * Water coolant material 17 = 1 * Zr-4 cladding * material 18 6.6000 610.61 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 * Previous line replaced by the following. Stainless steel material 18 7.9000 571.15 2 Fe 68.7 Ni 11.1 Cr 18.4 Mn 1.8 * Water coolant material 19 = 1 xgrid 1 0.0350 14 1.4300 1 0.0350 ygrid 1 0.0350 14 1.4300 1 0.0350 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 5 15 put 1003 6 13 put 1004 8 9 put 1005 12 2 put 1006 4 13 7 13 10 13 13136111111 41013104 7 13766116 4474104 13 4
* Fuel rod 1, 3.0000 initial U235 %wt wrt heavy metal rodsub 1 1 0.4520 2 rodsub 1 2 0.5380 3 rodsub 1 3 0.0 4
* Fuel rod 2, 3.0000 initial U235 %wt wrt heavy metal rodsub 2 1 0.4520 5 rodsub 2 2 0.5380 6 rodsub 2 3 0.0 7
* Fuel rod 3, 3.0000 initial U235 %wt wrt heavy metal rodsub 3 1 0.4520 8 rodsub 3 2 0.5380 9 rodsub 3 3 0.0 10
* Fuel rod 4, 3.0000 initial U235 %wt wrt heavy metal rodsub 4 1 0.4520 11 rodsub 4 2 0.5380 12 rodsub 4 3 0.0 13
* Fuel rod 5, 3.0000 initial U235 %wt wrt heavy metal rodsub 5 1 0.4520 14 rodsub 5 2 0.5380 15 rodsub 5 3 0.0 16
* Guide tube rodsub 6 1 0.6380 17 rodsub 6 2 0.6778 18 rodsub 6 3 0.0 19 burn all begin
WINTER 2
***************************************************** * WINTER : print out file 4 for UNSMEAR data ***************************************************** print file 4 begin
WPERSEUS 2
***************************************************** * WPERSEUS : calculates collision probabilities ***************************************************** nxmesh 16
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 102 of 115 RAT 1972 Issue 02 RAWG/P(01)04 nymesh 16 nslab 1 nrods 0 6 3 1 endpre xgrid 1 0.0350 14 1.4300 1 0.0350 ygrid 1 0.0350 14 1.4300 1 0.0350 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 5 15 put 1003 6 13 put 1004 8 9 put 1005 12 2 put 1006 4 13 7 13 10 13 13136111111 41013104 7 13766116 4474104 13 4
* Fuel rod 1, 3.0000 initial U235 %wt wrt heavy metal rodsub 1 1 0.4520 2 rodsub 1 2 0.5380 3 rodsub 1 3 0.0 4
* Fuel rod 2, 3.0000 initial U235 %wt wrt heavy metal rodsub 2 1 0.4520 5 rodsub 2 2 0.5380 6 rodsub 2 3 0.0 7
* Fuel rod 3, 3.0000 initial U235 %wt wrt heavy metal rodsub 3 1 0.4520 8 rodsub 3 2 0.5380 9 rodsub 3 3 0.0 10
* Fuel rod 4, 3.0000 initial U235 %wt wrt heavy metal rodsub 4 1 0.4520 11 rodsub 4 2 0.5380 12 rodsub 4 3 0.0 13
* Fuel rod 5, 3.0000 initial U235 %wt wrt heavy metal rodsub 5 1 0.4520 14 rodsub 5 2 0.5380 15 rodsub 5 3 0.0 16
* Guide tube rodsub 6 1 0.6380 17 rodsub 6 2 0.6778 18 rodsub 6 3 0.0 19 begin
WPIP 2
********************************************************* * WPIP : calculate fluxes from collision probabilities * and cross-sections ********************************************************* omega 1.25 tolerance 1.0e-5 begin
WCONDENSE 2 3
**************************************************************** * WCONDENSE : condense cross-sections and fluxes to 12 groups **************************************************************** groups 6 endprel energy 821000 9118 4 0.625 0.14 0 begin fface 5 * read and write fluxes to interface 5 WCACTUS 3
***************************************************** * WCACTUS : solve the diffusion equations ***************************************************** nxmesh 16
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 103 of 115 RAT 1972 Issue 02 RAWG/P(01)04 nymesh 16 nrods 256 6 3 angles 5 2 dump * dump the fluxes to the interface miss 1 1 * miss the restart on cycle 1 as no data in the interface restart * read the fluxes from the interface as an initial guess endp geomin xgrid 1 0.0350 14 1.4300 1 0.0350 ygrid 1 0.0350 14 1.4300 1 0.0350 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 5 15 put 1003 6 13 put 1004 8 9 put 1005 12 2 put 1006 4 13 7 13 10 13 13136111111 41013104 7 13766116 4474104 13 4
* Fuel rod 1, 3.0000 initial U235 %wt wrt heavy metal rodsub 1 1 0.4520 2 rodsub 1 2 0.5380 3 rodsub 1 3 0.0 4
* Fuel rod 2, 3.0000 initial U235 %wt wrt heavy metal rodsub 2 1 0.4520 5 rodsub 2 2 0.5380 6 rodsub 2 3 0.0 7
* Fuel rod 3, 3.0000 initial U235 %wt wrt heavy metal rodsub 3 1 0.4520 8 rodsub 3 2 0.5380 9 rodsub 3 3 0.0 10
* Fuel rod 4, 3.0000 initial U235 %wt wrt heavy metal rodsub 4 1 0.4520 11 rodsub 4 2 0.5380 12 rodsub 4 3 0.0 13
* Fuel rod 5, 3.0000 initial U235 %wt wrt heavy metal rodsub 5 1 0.4520 14 rodsub 5 2 0.5380 15 rodsub 5 3 0.0 16
* Guide tube rodsub 6 1 0.6380 17 rodsub 6 2 0.6778 18 rodsub 6 3 0.0 19 qual 1 1 picture endgeom azimuthal 5 0.1 polar 2 begin
FFACE 2 WUNSMEAR 3 2
******************************************************** * WUNSMEAR : unsmear the cross-sections and fluxes * ********************************************************
nmesh 1 umesh 1 smesh mate 2 nmesh 2 umesh 2 smesh mate 3 nmesh 3 umesh 3 smesh mate 4 nmesh 4 umesh 4 smesh mate 5 nmesh 5 umesh 5 smesh mate 6 nmesh 6 umesh 6 smesh mate 7 nmesh 7 umesh 7 smesh mate 8 nmesh 8 umesh 8 smesh mate 9 nmesh 9 umesh 9 smesh mate 10 nmesh 10 umesh 10 smesh mate 11 nmesh 11 umesh 11 smesh mate 12 nmesh 12 umesh 12 smesh mate 13 nmesh 13 umesh 13 smesh mate 14
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 104 of 115 RAT 1972 Issue 02 RAWG/P(01)04
nmesh 14 umesh 14 smesh mate 15 nmesh 15 umesh 15 smesh mate 16 nmesh 16 umesh 16 smesh mate 17 nmesh 17 umesh 17 smesh mate 18 nmesh 18 umesh 18 smesh mate 19 nmesh 19 umesh 19 smesh mate 1 begin
***************************************************** * A blank line MUST precede the WEDIT codeword * *****************************************************
WEDIT 3
***************************************************** * WEDIT : output the masses of the actinides * ***************************************************** materials2581114 nuclides actinides masses norm 2.900000E+07 power reactions fission power rates begin
WINTER 2 30 0 1
******************************************************************* * WINTER - copy interface 2 for TRAIL input ******************************************************************* copy begin print 1 WBRNUP 3 1
******************************************************************* * WBRNUP - Perform burnup calculation and change number densities ******************************************************************* rating 1 29.00000 qual 1 1 -4 steps 1 0.500000 qual 1 5 steps 2 2.448276 qual 1 6 steps 3 3.448276 qual 1 7 steps 5 3.448276 qual 1 8 steps 5 6.896552 qual 1 9 -12 steps 10 6.896552 qual 1 13 -19 steps 10 17.241379 trigger 11 alpha PU240 900.00 radius 0.4520 fuel 2 5 8 11 14 alpha PU242 900.00 radius 0.4520 fuel 2 5 8 11 14 begin print 0 finish stop
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 105 of 115 RAT 1972 Issue 02 RAWG/P(01)04
PWR: Calvert Cliffs – ATM-104
******************************************************************* * WIMS case created by WICID 6.2. * * Station : Calvert_Cliffs_2 * Pin Map : ATM-104-MKP109 * Fuel type : UOX * Final Irradiation (MWd/t) : 50000.00000 * Rating (MW/t) : 22.00000 * Initial U235 enrichment (%wt) : 3.03800 * * Modifications * Smeared guide tube and water * Burnup steps * TRIGGER *******************************************************************
NCYCLE 1 21
WHEAD 1 2
******************************************************************* * WHEAD - Define geometry and calculate macroscopic cross sections ******************************************************************* nmaterials 8 nxmesh 16 nymesh 16 nslab 2 nrods 0 2 3 1 endpre
* Water gap - Boron content (ppm) 451.00 material 1 0.72975 571.15 3 H 1.1189E+01 O 8.8766E+01 B 4.5100E-02
* Water pin material 2 1.32387 571.15 3 Zr 4.95482E-01 Sn 7.56846E-03 Fe 1.00913E-03 Cr 5.04564E-04 H 5.54343E-02 O 4.39778E-01 B 2.23441E-04
* Pin type 1, 3.0380 initial U235 %wt, fuel/clad/coolant material 3 10.0590 835.00 1 U234 2.3787E-02 U235 2.6781E+00 U236 1.3223E-02 U238 8.5437E+01 O 1.1848E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 4 5.4843 602.81 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 5 = 1
* Pin type 2, 3.0380 initial U235 %wt, fuel/clad/coolant material 6 10.0590 835.00 1 U234 2.3787E-02 U235 2.6781E+00 U236 1.3223E-02 U238 8.5437E+01 O 1.1848E+01 * Clad (smeared into the pellet-clad gap) * Zr-4 cladding material 7 5.4843 602.81 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 material 8 = 1 xgrid 1 0.0776 14 1.4732 1 0.0776 ygrid 1 0.0776 14 1.4732 1 0.0776 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 8 13 put 2 4135131213 13 13 4 12 5 12 12 12 13 12 8 9 998898 4555125 1354454 12 4 13 4
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 106 of 115 RAT 1972 Issue 02 RAWG/P(01)04
* Fuel rod 1, 3.0380 initial U235 %wt wrt heavy metal rodsub 1 1 0.4782 3 rodsub 1 2 0.5590 4 rodsub 1 3 0.0 5
* Fuel rod 2, 3.0380 initial U235 %wt wrt heavy metal rodsub 2 1 0.4782 6 rodsub 2 2 0.5590 7 rodsub 2 3 0.0 8 burn all begin
WINTER 2
***************************************************** * WINTER : print out file 4 for UNSMEAR data ***************************************************** print file 4 begin
WPERSEUS 2
***************************************************** * WPERSEUS : calculates collision probabilities ***************************************************** nxmesh 16 nymesh 16 nslab 2 nrods 0 2 3 1 endpre xgrid 1 0.0776 14 1.4732 1 0.0776 ygrid 1 0.0776 14 1.4732 1 0.0776 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 8 13 put 2 4135131213 13 13 4 12 5 12 12 12 13 12 8 9 998898 4555125 1354454 12 4 13 4
* Fuel rod 1, 3.0380 initial U235 %wt wrt heavy metal rodsub 1 1 0.4782 3 rodsub 1 2 0.5590 4 rodsub 1 3 0.0 5
* Fuel rod 2, 3.0380 initial U235 %wt wrt heavy metal rodsub 2 1 0.4782 6 rodsub 2 2 0.5590 7 rodsub 2 3 0.0 8 begin
WPIP 2
********************************************************* * WPIP : calculate fluxes from collision probabilities * and cross-sections ********************************************************* omega 1.25 tolerance 1.0e-5 begin
WCONDENSE 2 3
**************************************************************** * WCONDENSE : condense cross-sections and fluxes to 12 groups **************************************************************** groups 6 endprel energy 821000 9118 4 0.625 0.14 0 begin
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 107 of 115 RAT 1972 Issue 02 RAWG/P(01)04 fface 5 * read and write fluxes to interface 5 WCACTUS 3
***************************************************** * WCACTUS : solve the diffusion equations ***************************************************** nxmesh 16 nymesh 16 nrods 256 2 3 angles 5 2 dump * dump the fluxes to the interface miss 1 1 * miss the restart on cycle 1 as no data in the interface restart * read the fluxes from the interface as an initial guess endp geomin xgrid 1 0.0776 14 1.4732 1 0.0776 ygrid 1 0.0776 14 1.4732 1 0.0776 map 1 1 16 1 16 map 1001 2 15 2 15 put 1002 8 13 put 2 4135131213 13 13 4 12 5 12 12 12 13 12 8 9 998898 4555125 1354454 12 4 13 4
* Fuel rod 1, 3.0380 initial U235 %wt wrt heavy metal rodsub 1 1 0.4782 3 rodsub 1 2 0.5590 4 rodsub 1 3 0.0 5
* Fuel rod 2, 3.0380 initial U235 %wt wrt heavy metal rodsub 2 1 0.4782 6 rodsub 2 2 0.5590 7 rodsub 2 3 0.0 8 qual 1 1 picture endgeom azimuthal 5 0.1 polar 2 begin
FFACE 2 WUNSMEAR 3 2
******************************************************** * WUNSMEAR : unsmear the cross-sections and fluxes * ********************************************************
nmesh 1 umesh 1 smesh mate 3 nmesh 2 umesh 2 smesh mate 4 nmesh 3 umesh 3 smesh mate 5 nmesh 4 umesh 4 smesh mate 6 nmesh 5 umesh 5 smesh mate 7 nmesh 6 umesh 6 smesh mate 8 nmesh 7 umesh 7 smesh mate 1 nmesh 8 umesh 8 smesh mate 2 begin
***************************************************** * A blank line MUST precede the WEDIT codeword * *****************************************************
WEDIT 3
***************************************************** * WEDIT : output the masses of the actinides * ***************************************************** materials 3 6 nuclides actinides masses norm 2.200000E+07 power reactions fission power rates begin
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 108 of 115 RAT 1972 Issue 02 RAWG/P(01)04
WINTER 2 30 0 1
******************************************************************* * WINTER - copy interface 2 for TRAIL input ******************************************************************* copy begin print 1 WBRNUP 3 1
******************************************************************* * WBRNUP - Perform burnup calculation and change number densities ******************************************************************* rating 1 22.00000 qual 1 1 -4 steps 1 0.500000 qual 1 5 steps 2 3.545455 qual 1 6 steps 3 4.545455 qual 1 7 steps 5 4.545455 qual 1 8 steps 5 9.090909 qual 1 9 -12 steps 10 9.090909 qual 1 13 -21 steps 10 22.727273 trigger 6 alpha PU240 835.00 radius 0.4782 fuel 3 6 alpha PU242 835.00 radius 0.4782 fuel 3 6 begin print 0 finish stop
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 109 of 115 RAT 1972 Issue 02 RAWG/P(01)04
PWR: Goesgen – Sample GU1
********************************************* * WIMS8 input for GOSGEN PWR for ARIANE * * Sample : GU1 in assembly 12-40 * (4 cycles - 12,13,14 & 15) * * Triggers option to include sample burnup * * Based upon 00047w811 with the following modifications * condense groups changed to 69 group structure * print 1 before burnup * short steps at beginning of burnup * comments upon replacement rods * ratings based on elapsed days * ********************************************* ncycle 1 71 WHEAD 1 2 nmaterials 19 nxmesh 17 nymesh 17 nslab 1 nrods0631 endpre
******************************************** * Pin and Assembly Pitch from ARIANE * Irradiation Data Report Part 1 ******************************************** xgrid 1 0.055 15 1.43 1 0.055 ygrid 1 0.055 15 1.43 1 0.055 map1117117
********************************************* * 15x15 Fuel Rods added ********************************************* map 1002 2 16 2 16
********************************************* * Guide tube positions ********************************************* put10034447411414 put10036669612 put100374714 put100396912 put 1003 11 4 11 14 put 1003 12 6 12 9 12 12 put 1003 14 4 14 7 14 11 14 14
********************************************* * GU1 in the following pin for assembly * irradiation cycles 12/13/14/15 ********************************************* put 1001 12 4
******************************************** * Rods replaced in reactor cycle 14 ******************************************** put 1004 11 5 12 5
******************************************** * Rods replaced in reactor cycle 15 ******************************************** put 1005 11 3 12 3
******************************************** * Rod replaced in reactor cycle 14+15 ******************************************** put 1006 13 5
********************************************* * Water for gap ********************************************* mate 1 0.706 582.15 3 H 11.185 O 88.734 B 8.0876E-02 ********************************************* * 3.5% U-235 Rod - GU1 *********************************************
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 110 of 115 RAT 1972 Issue 02 RAWG/P(01)04
URANIUM U235 3.5E+00 U238 9.6464E+01 U234 3.6E-02 PLUS O 2.0 mate 2 10.4 947.7 1 U 100.0
********************************************* * Zr smeared clad - needs amending? ********************************************* mate 3 5.9579 626.0 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1
********************************************* * Water around rods ********************************************* mate4=1
********************************************* * 3.5% U-235 rod * Density and Pin Enrichment from * ARIANE irradiation report part 2 ******************************************** mate5=2 mate6=3 mate7=4
********************************************* * Guide tube ********************************************* mate8=4 mate 9 6.6 582.15 2 Zr 98.2 Sn 1.5 Fe 0.2 Cr 0.1 mate 10 = 4
********************************************* * Rods replaced in reactor cycle 14 ********************************************* mate 11 = 2 mate 12 = 3 mate 13 = 4
********************************************* * Rods replaced in reactor cycle 15 ********************************************* mate 14 = 2 mate 15 = 3 mate 16 = 4
********************************************* * Rod replaced in reactor cycle 14 + 15 ********************************************* mate 17 = 2 mate 18 = 3 mate 19 = 4
******************************************** * 3.5% U-235 rod - GU1 * Cladding (inner and outer) and pellet * diameter from ARIANE irradiation report * part-1 ********************************************* rodsub 1 1 0.4565 2 rodsub 1 2 0.5375 3 rodsub130.0 4
******************************************** * 3.5% U-235 rod ******************************************** rodsub 2 1 0.4565 5 rodsub 2 2 0.5375 6 rodsub230.0 7
******************************************** * Guide tube ******************************************** rodsub 3 1 0.6200 8 rodsub 3 2 0.6900 9 rodsub 3 3 0.0 10
******************************************** * Rods replaced in reactor cycle 14 ******************************************** rodsub 4 1 0.4565 11 rodsub 4 2 0.5375 12 rodsub 4 3 0.0 13
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 111 of 115 RAT 1972 Issue 02 RAWG/P(01)04
******************************************** * Rods replaced in reactor cycle 15 ******************************************** rodsub 5 1 0.4565 14 rodsub 5 2 0.5375 15 rodsub 5 3 0.0 16
********************************************* * Rod replaced in reactor cycle 14 + 15 ********************************************* rodsub 6 1 0.4565 17 rodsub 6 2 0.5375 18 rodsub 6 3 0.0 19
******************************************** * Reactor cycle 12 and 13 ******************************************** qual 3 1 -41 burn all
******************************************** * add fresh fuel on cycle 14 ******************************************** qual 6 42 URANIUM U235 3.5E+00 U238 9.6464E+01 U234 3.6E-02 PLUS O 2.0 mate 11 10.4 947.7 1 U 100.0 mate 17 = 11 burn all 11 17 qual 1 43 -56 burn all
******************************************** * add fresh fuel on cycle 15 ******************************************** qual 6 57 URANIUM U235 3.5E+00 U238 9.6464E+01 U234 3.6E-02 PLUS O 2.0 mate 14 10.4 947.7 1 U 100.0 mate 17 = 14 burn all 14 17 qual 1 58 -71 burn all
******************************************** * End ******************************************** begin
******************************************* * WINTER : print file 4 for UNSMEAR data * ******************************************* WINTER 2 print file 4 begin
******************************************* * WPERSEUS : calc collision probabilities * ******************************************* WPERS 2 nxmesh 17 nymesh 17 nslab 1 nrods0631 endpre xgrid 1 0.055 15 1.43 1 0.055 ygrid 1 0.055 15 1.43 1 0.055 map1117117 map 1002 2 16 2 16 put10034447411414 put10036669612 put100374714 put100396912 put 1003 11 4 11 14 put 1003 12 6 12 9 12 12
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 112 of 115 RAT 1972 Issue 02 RAWG/P(01)04 put 1003 14 4 14 7 14 11 14 14 put 1001 12 4 ******************************************** * Rods replaced in reactor cycle 14 ******************************************** put 1004 11 5 12 5 ******************************************** * Rods replaced in reactor cycle 15 ******************************************** put 1005 11 3 12 3 ******************************************** * Rod replaced in reactor cycle 14+15 ******************************************** put 1006 13 5 rodsub 1 1 0.4565 2 rodsub 1 2 0.5375 3 rodsub130.0 4 rodsub 2 1 0.4565 5 rodsub 2 2 0.5375 6 rodsub230.0 7 rodsub 3 1 0.6200 8 rodsub 3 2 0.6900 9 rodsub 3 3 0.0 10 rodsub 4 1 0.4565 11 rodsub 4 2 0.5375 12 rodsub 4 3 0.0 13 rodsub 5 1 0.4565 14 rodsub 5 2 0.5375 15 rodsub 5 3 0.0 16 rodsub 6 1 0.4565 17 rodsub 6 2 0.5375 18 rodsub 6 3 0.0 19 begin
******************************************* * WPIP : calc fluxes * ******************************************* WPIP 2 omega 1.25 tolerance 1.0e-05 begin
******************************************* * WCONDENSE : condense fluxes & c.secs * ******************************************* WCONDENSE 2 3 groups 6 endp energy 821000 9118 4 0.625 0.14 0 begin
******************************************* * WCACTUS : Solve the diffusion equation * ******************************************* FFACE 5 WCACTUS 3 nxmesh 17 nymesh 17 nrods 289 6 3 angles 5 2 dump miss 1 1 restart endp geometry xgrid 1 0.055 15 1.43 1 0.055 ygrid 1 0.055 15 1.43 1 0.055 map1117117 map 1002 2 16 2 16 put10034447411414 put10036669612 put100374714 put100396912 put 1003 11 4 11 14 put 1003 12 6 12 9 12 12 put 1003 14 4 14 7 14 11 14 14 put 1001 12 4 ******************************************** * Rods replaced in reactor cycle 14 ******************************************** put 1004 11 5 12 5 ******************************************** * Rods replaced in reactor cycle 15
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 113 of 115 RAT 1972 Issue 02 RAWG/P(01)04
******************************************** put 1005 11 3 12 3 ******************************************** * Rods replaced in reactor cycle 14+15 ******************************************** put 1006 13 5 rodsub 1 1 0.4565 2 rodsub 1 2 0.5375 3 rodsub130.0 4 rodsub 2 1 0.4565 5 rodsub 2 2 0.5375 6 rodsub230.0 7 rodsub 3 1 0.6200 8 rodsub 3 2 0.6900 9 rodsub 3 3 0.0 10 rodsub 4 1 0.4565 11 rodsub 4 2 0.5375 12 rodsub 4 3 0.0 13 rodsub 5 1 0.4565 14 rodsub 5 2 0.5375 15 rodsub 5 3 0.0 16 rodsub 6 1 0.4565 17 rodsub 6 2 0.5375 18 rodsub 6 3 0.0 19 qual 1 1 pict endgeom azim 5 0.1 polar 2 begin
******************************************* * WUNSMEAR : unsmear fluxes & c.sections * ******************************************* FFACE 2 WUNSMEAR 3 2 nmesh 1 umesh 1 smesh mate 2 nmesh 2 umesh 2 smesh mate 3 nmesh 3 umesh 3 smesh mate 4 nmesh 4 umesh 4 smesh mate 5 nmesh 5 umesh 5 smesh mate 6 nmesh 6 umesh 6 smesh mate 7 nmesh 7 umesh 7 smesh mate 8 nmesh 8 umesh 8 smesh mate 9 nmesh 9 umesh 9 smesh mate 10 nmesh 10 umesh 10 smesh mate 11 nmesh 11 umesh 11 smesh mate 12 nmesh 12 umesh 12 smesh mate 13 nmesh 13 umesh 13 smesh mate 14 nmesh 14 umesh 14 smesh mate 15 nmesh 15 umesh 15 smesh mate 16 nmesh 16 umesh 16 smesh mate 17 nmesh 17 umesh 17 smesh mate 18 nmesh 18 umesh 18 smesh mate 19 nmesh 19 umesh 19 smesh mate 1 begin
******************************************* * WEDIT : output mass data to output file * *******************************************
WEDIT 3 materials25111417 nuclides all masses norm 1 fissions reactions fission power rates begin
******************************************* * WINTER : copy interfaces for TRAIL * ******************************************* WINTER 2 30 0 1 copy begin print 1 ******************************************* * WBRNUP : perform burnup calculation * ******************************************* WBRNUP 3 1 endp
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 114 of 115 RAT 1972 Issue 02 RAWG/P(01)04 alpha Pu240 947.7 radius 0.4565 fuel 2 5 11 14 17 alpha Pu242 947.7 radius 0.4565 fuel 2 5 11 14 17
****************** * REACTOR CYCLE 12 ****************** qual 1 1 -25 rating 1 56.5121
* irradiate to 1000 MWd/t qual11-4 step 1 0.500000 qual 1 5 step 2 0.769533 qual 1 6 step 3 1.769533 qual 1 7 step 5 1.769533
* irradiate to 10000 MWd/t qual 1 8 -16 step 5 3.539065
* irradiate to 18000 MWd/t in 1 GWd/t steps qual 1 17 -24 step 2 8.847663
* irradiate to 18649 MWd/t in a 0.649 GWd/t step qual 1 25 step 2 5.742133
****************** * REACTOR CYCLE 13 ****************** qual 1 26 -41 rating 1 45.0151
* irradiate to 19000 MWd/t in a 0.351 GWd/t step qual 1 26 step 1 7.797384
* irradiate to 33000 MWd/t in 1 GWd/t steps qual 1 27 -40 step 2 11.107384
* irradiate to 33594 MWd/t in a 0.594 GWd/t step qual 1 41 step 2 6.597786
****************** * REACTOR CYCLE 14 ****************** qual 1 42 -56 rating 1 40.3296
* irradiate to 34000 MWd/t in a 0.406 GWd/t step qual 1 42 step 1 10.067048
* irradiate to 47000 MWd/t in 1 GWd/t steps qual 1 43 -55 step 2 12.397842
* irradiate to 47911 MWd/t in a 0.911 GWd/t step qual 1 56 step 2 11.294434
****************** * REACTOR CYCLE 15 ****************** qual 1 57 -71 rating 1 34.7485
* irradiate to 48000 MWd/t in a 0.089 GWd/t step
IMC Only NCPEXT/00-01/1/rep/2 IMC Only Page 115 of 115 RAT 1972 Issue 02 RAWG/P(01)04 qual 1 57 step 1 2.561262
* irradiate to 61000 MWd/t in 1 GWd/t steps (>59656) qual 1 58 -71 step 2 14.389110
***** * END *****
TRIGGER 2 begin print 0 finish stop
IMC Only NCPEXT/00-01/1/rep/2