Overview of Nuclear Data

Michal Herman National Nuclear Data Center Brookhaven National Laboratory Nuclear Data Program Link between basic science and applications

Nuclear Science Community ✦ experiments

Eur. Phys.✦ J.theory A (2012) 48:113 Page 11 of 39

10Nuclear2 Data Application Cross section (barn)

10Community Community ✦ natural needs data: compilationLu(n,γ) @ DANCE 1 ENDF/B−VII.0 SAMMY7.0 broadened and fitted

10−1 1 10 102 ✦ ✦ evaluation Neutron energy (eV) complete Fig. 15. Cross-section for the 175Lu(n, γ) reaction measured with a natural Lutetium sample in the resolved resonance ✦ organized ✦range.archival

176Lu(n,γ) @ DANCE ✦ 104 ENDF/B−VII.0 SAMMY7 broadened and fitted traceable DANCE detector ✦ dissemination 103 ✦ readable

LANSCE Cross section (barn)

102 Fig. 14. The DANCE detector (picture credits: LANSCE-NSM. Herman Berkeley, May 27-19, 2015 LA-UR-0802953). 10

1 processed into physical quantities, like the total γ cascade 10−1 1 10 102 energy, γ multiplicity, individual gamma ray energies, and Neutron energy (eV) neutron time of flight. After analysis of these data and sev- 176 eral corrections (calibration, dead time correction, back- Fig. 16. Cross-section for the Lu(n, γ)reactioninthere- solved resonance range. ground subtraction) the neutron radiative capture cross- section σ(n,γ)(En) is obtained. Results are presented here 176 2 Lu(n,γ) @ DANCE for three energy ranges: i) thermal energy, ii) resolved res- 10 onance region, and iii) above 1 keV in the unresolved res- ENDF/B−VII.0 onance region. K. Wisshak et al, 2006 H. Beer et al, 1984 i) For an incident neutron energy of 0.025 eV, the mea- BRC sured cross-sections for 175Lu(n, γ)and176Lu(n, γ), are in Cross section (barn) good agreement with published values [64] while improv- 10 ing their precisions. The thermal capture cross-sections of Lu are important for nuclear reactors, where they are used to measure the core temperature. ii) The analysis of the neutron capture experimental 1 data in the resolved resonance region allows the determi- nation of the energies of resonances as well as their radia- tive and neutron widths, and spins. For that purpose, we 102 103 104 Neutron energy (eV) rely on a R-matrix code to fit the experimental cross-sec- tions and determine the characteristics of the resonances. Fig. 17. Cross-section for the 176Lu(n, γ)reactioninthecon- Figures 15 and 16 display the radiative capture cross-sec- tinuum energy region. tions measured for 175Lu and 176Lu, respectively. These new measurements agree with previous experiments [65, 66]. Moreover, since γ multiplicities have been measured, performed in the continuum (using the Hauser-Feshbach spin values could be attributed to several resonances. model). In the resolved resonances domain, the analysis of mea- iii) For the Lu isotopes, the unresolved resonance re- sured data allowed to extract values of the mean radia- gion extends from a few keV to 1 MeV. Unlike the re- tive width ( Γ ), the mean s-wave level spacing (D ) solved resonance region where models only produce a ⟨ γ ⟩ 0 and neutron strength function (S0). These values are use- parametrization of experimental data, continuum mod- ful for connecting the evaluations performed in the re- els like the optical model potential can describe experi- solved resonance region (using R-matrix) with evaluations mental data in a more predictive way. Figure 17 displays Who needs nuclear data? and what for?

Nuclear medicine Basic science (physics) radioisotope production testing theoretical models dose calculation designing experiments radiotherapy analyzing experimental data diagnostics Astrophysics National/homeland origin of elements security Nuclear power device R&D reactors R&D stockpile stewardship fuel cycle criticality safety operation safety nuclear forensics radiation shielding detecting illicit trafficking of waste disposal and nuclear materials transmutation Industrial applications

M. Herman Berkeley, May 27-19, 2015 USNDP mission

The mission of the United States Nuclear Data Program (USNDP) is to provide current, accurate, authoritative data for workers in pure and applied areas of nuclear science and engineering. This is accomplished primarily through the compilation, evaluation, dissemination, and archiving of extensive nuclear datasets. The USNDP also addresses gaps in the data, through targeted experimental studies and the use of theoretical models.

Dissemination Archival Evaluation/ Experiments Theory Compilation

M. Herman Berkeley, May 27-19, 2015 Components of Nuclear Data

Structure Reactions Dissemination Bibliographical NSR Obviously indispensable

Compilation XUNDL EXFOR

Evaluated ENSDF ENDF/B Archival Obviously essential

Evaluation/ Experiments Theory Using external facilities Ultimate nuclear data product - ~15% of USNDP effort combines experiment with theory, Compilation links basic science with applications, includes modeling and covariances, Needs continuous coverage high added value! Backlog needs to be dealt with

M. Herman Berkeley, May 27-19, 2015 Structure & Reactions Objectives Decay Bibliographical NSR database >214,000 publications Compilation XUNDL EXFOR Experiments - form the basis databases 5,622 datasets 20,400 experiments of what we do and we also contribute. Evaluated Compilation - reaction and ENSDF ENDF/B-VII.1 3,256 isotopes 14 sub-libraries nuclear structure data in NSR, libraries EXFOR and XUNDL databases. Evaluation/Theory - nuclear structure and reaction data for ENSDF and ENDF/B databases. Advance nuclear reaction modeling; uncertainty quantification. Maintain/develop nuclear data formats and data verification codes. Archival of nuclear data (maintaining classic library, gradually scanning it into electronic files, securing electronic files). Dissemination of nuclear physics data using up to date technology..

M. Herman Berkeley, May 27-19, 2015 ND libraries

ACE Wallet cards FENDL POINT MIRD 20XX Cap Gam NG EGAF Atlas

Atlas neutr. Neutron Isomeric Masses resonances Standards levels ENDF ENSDF Delayed Dosimetry B(E2) neutrons

Codes EXFOR XUNDL RIPL

NSR

Experiments

M. Herman Berkeley, May 27-19, 2015 Interaction between ND libraries (ENSDF)

ENSDF EGAF Masses

EXFOR XUNDL

NSR

Experiments

M. Herman Berkeley, May 27-19, 2015 ND libraries

ACE Wallet cards FENDL POINT MIRD 20XX Cap Gam NG EGAF Atlas

Atlas neutr. Neutron Isomeric Masses resonances Standards levels ENDF ENSDF Delayed Dosimetry B(E2) neutrons

Codes EXFOR XUNDL RIPL

NSR

Experiments

M. Herman Berkeley, May 27-19, 2015 Interaction between ND libraries (ENDF)

Atlas neutr. resonances ENDF ENSDF Neutron Masses Standards Dosimetry

EGAF Codes EXFOR

RIPL

NSR

Experiments

M. Herman Berkeley, May 27-19, 2015 ND libraries

ACE Wallet cards FENDL POINT MIRD 20XX Cap Gam NG EGAF Atlas

Atlas neutr. Neutron Isomeric Masses resonances Standards levels ENDF ENSDF Delayed Dosimetry B(E2) neutrons

Codes EXFOR XUNDL RIPL

NSR

Experiments

M. Herman Berkeley, May 27-19, 2015 Components of Nuclear Data program

Structure Reactions Dissemination Bibliographical NSR

Compilation XUNDL EXFOR

Evaluated ENSDF ENDF/B Archival

Evaluation/ Experiments Theory Using external facilities ~15% of USNDP effort Compilation

M. Herman Berkeley, May 27-19, 2015 Experimental Nuclear Data

Program Gammasphere at ANL

HIγS

DANCE at LANSCE

M. Herman Berkeley, May 27-19, 2015 Why USNDP Needs Experimental

Program (on a small scale)?

Perform measurements targeting specific needs USNDP is in unique position to identify deficiencies in nuclear data Faster response in remedying deficiencies in database Stronger link between data community and research groups Maintain USNDP staff current with advancing experimental techniques Promoting nuclear data awareness within research community Combined evaluation and experimental research opportunities Attract new talents to nuclear data program

M. Herman Berkeley, May 27-19, 2015

Components of Nuclear Data program

Structure Reactions Dissemination Bibliographical NSR

Compilation XUNDL EXFOR

Evaluated ENSDF ENDF/B Archival

Using external facilities cost - mostlyEvaluation/ travel Experiments Theory

Compilation Needs continuous coverage

M. Herman Berkeley, May 27-19, 2015 ENSDF

Structure & Reactions Decay Bibliographical NSR database >214,000 publications Compilation XUNDL EXFOR databases ~5,600 datasets ~20,400 experiments

Groundwork for any evaluation Preserves multibillion $$$$ investment in nuclear experiments over a century Often goes beyond the publication

M. Herman Berkeley, May 27-19, 2015 Components of Nuclear Data program

Structure Reactions Dissemination Bibliographical NSR

Compilation XUNDL EXFOR

Evaluated ENSDF ENDF/B Archival

Evaluation/ Experiments Theory Ultimate nuclear data product combines experiment with theory Compilation links basic science with applications includes modeling and covariances high added value!

M. Herman Berkeley, May 27-19, 2015 Nuclear structure and reaction data are complementary

Reaction data: EXFOR (compiled) ENDF (evaluated)

Structure data: XUNDL (compiled) ENDSF (evaluated)

M. Herman Berkeley, May 27-19, 2015 Nuclear structure and reaction data are complementary

Reaction data: EXFOR (compiled) ENDF (evaluated)

reactions

structure

Structure data: XUNDL (compiled) ENDSF (evaluated)

M. Herman Berkeley, May 27-19, 2015 Nuclear structure and reaction data are complementary

Decay data: Reaction data: ENDF Decay EXFOR (compiled) Sublibrary (evaluated) ENDF (evaluated)

reactions

structure

Structure data: XUNDL (compiled) ENDSF (evaluated)

M. Herman Berkeley, May 27-19, 2015 Nuclear structure and reaction data are complementary

Reaction data: EXFOR (experimental) ENDF (evaluated)

reactions

structure

Structure data: XUNDL (compiled) ENDSF (evaluated)

M. Herman Berkeley, May 27-19, 2015 Nuclear structure and decay data evaluated: ENSDF compiled: XUNDL

Nuclear Structure (ENSDF) masses properties of nuclear levels energies spins & parities magnetic moments half-lives deformations decay modes intensities (branching ratios) conversion coefficients … radiation properties Contributed by members of the Nuclear Structure and Decay Data Network (NSDD), under auspices of the IAEA.

M. Herman Berkeley, May 27-19, 2015 ENSDF’s seminal role in science & applications The only Nuclear Structure database that is updated continuously contains information for all nuclei and all nuclear level properties & radiations No viable alternative exists in the world! Thanks to F. Kondev

Applications ENSDF Basic NP Research JEFF, JENDL, …

ORTEC & CANBERRA Simulations RIPL MIRD Monte-Carlo Codes MCNP, IE RNAL GEANT, EGS4 EEAF NuDat astrophysics ORIGEN, CINDER90 PGAA NUBASE

M. Herman Berkeley, May 27-19, 2015 Reaction data: EXFOR (compiled) ENDF (evaluated)

reactions

structure

Structure data: XUNDL (compiled) ENDSF (evaluated)

M. Herman Berkeley, May 27-19, 2015 Nuclear reaction data evaluated: ENDF/B energy-dependent reaction cross sections energy and angular distributions of reaction products energy-angle distributions neutron resonance param. Volume 112, Number 12, December 2011 ISSN 0090-3752 neutron multiplicities Nuclear isomeric cross sections ... Data Sheets

A Journal Devoted to Compilations and Evaluations of Experimental and Theoretical Results in Nuclear Physics

J.K. Tuli National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000, USA www.nndc.bnl.gov

Special Issue on ENDF/B-VII.1 Library

Special Issue Editor: Pavel Obložinský

Contents

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Thermal Covariances, Fission Product Yields and Decay Data….……..………………………...... 2887 M.B. Chadwick, M. Herman, P. Obložinský, M.E. Dunn, Y. Danon, A.C. Kahler, D.L. Smith, B. Pritychenko, G. Arbanas, R. Arcilla, R. Brewer, D.A. Brown, R. Capote, A.D. Carlson, Y.S. Cho, H. Derrien, K. Guber, G.M. Hale, S. Hoblit, S. Holloway, Fast T.D. Johnson, T. Kawano, B.C. Kiedrowski, H. Kim, S. Kunieda, N.M. Larson, L. Leal, J.P. Lestone, R.C. Little, E.A. McCutchan, R.E. MacFarlane, M. MacInnes, C.M. Mattoon, R.D. McKnight, S.F. Mughabghab, G.P.A. Nobre, G. Palmiotti, A. Palumbo, M.T. Pigni, V.G. Pronyaev, R.O. Sayer, A.A. Sonzogni, N.C. Summers, P. Talou, I.J. Thompson, A. Trkov, R.L. Vogt, S.C. van der Marck, A. Wallner, M.C. White, D. Wiarda, P.G. Young neutron ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments…………..………………..…….……………..….2997 A. C. Kahler, R. E. MacFarlane, R. D. Mosteller, B. C. Kiedrowski, S. C. Frankle, M. B. Chadwick, R. D. McKnight, R. M. Lell, G. Palmiotti, H. Hiruta, M. Herman, R. Arcilla, S. F. Mughabghab, J. C. Sublet, A. Trkov, T. H. Trumbull, and M. Dunn

Resonances ENDF/B-VII.1Contents continues on the back cover page

released Dec. 2011

M. Herman Berkeley, May 27-19, 2015 ENDF/B-VII.1 Nuclear Data ... NUCLEAR DATA SHEETS M.B. Chadwick et al.

IV. OVERVIEW OF ENDF/B-VII.1 LIBRARY 1. The photonuclear sublibrary was carried over un- changed from ENDF/B-VII.0. It contains evalu- A. Contents of ENDF/B-VII.1 ated cross sections for 163 materials (all isotopes) mostly up to 140 MeV. The sublibrary was supplied The ENDF/B-VII.1 library contains 14 sublibraries as by Los Alamos National Laboratory (LANL) and it summarized in Table I.Theyareorderedaccordingto is largely based on the IAEA-coordinated collabo- NSUB, the identification number of the sublibrary. The ration completed in 2000. number of materials (isotopes or elements) are given for 2. The photo-atomic sublibrary was taken over from both the new (VII.1) and previous (VII.0) versions of the ENDF/B-VII.0=ENDF/B-VI.8. It contains data ENDF/B library. for photons from 10 eV up to 100 GeV interacting with atoms for 100 materials (all elements). The sublibrary was supplied by Lawrence Livermore Na- TABLE I: Contents of the ENDF/B-VII.1 library, with tional Laboratory (LLNL). ENDF/B-VII.0 and ENDF/B-VI.8 shown for comparison. NSUB stands for the sublibrary number in the ENDF-6 for- 3. The decay data sublibrary has been re-evaluated Contentsmat. Given of in the last ENDF/B three columns (sub)libraries are the number of ma- and considerably improved by the Brookhaven Na- terials (isotopes or elements). tional Laboratory (BNL). 4. The spontaneous fission yields were taken over No. NSUB Sublibrary Short VII.1 VII.0 VI.8 from ENDF/B-VII.0=ENDF/B-VI.8. The data name name were supplied by LANL. 10Photonuclearg163163- 23Photo-atomicphoto100100100 34Radioactivedecaydecay381738389795. The atomic relaxation sublibrary was taken over 45Spont.fis.yieldss/fpy999 from ENDF/B-VII.0=ENDF/B-VI.8. It contains 56Atomicrelaxationard100100100 data for 100 materials (all elements) supplied by 610Neutronn 423393328 LLNL. 711Neutronfis.yieldsn/fpy313131 812Thermalscatteringtsl202015 6. The neutron reaction sublibrary represents the 919Standardsstd888 heart of the ENDF/B-VII.1 library. The subli- 10 113 Electro-atomic e 100 100 100 brary has been updated and extended, it contains 11 10010 Proton p 48 48 35 12 10020 Deuteron d 5 5 2 423 materials, including 422 isotopic and 1 elemen- 13 10030 Triton t 3 3 1 tal evaluation. A brief summary of the neutron 14 20030 3He he3 2 2 1 evaluations, particularly changes compared to the previous ENDF/B-VII.0 database, is given in Ta-

M. Herman Berkeley, May 27-19, 2015 ble III.Altogether234materialshavebeenchanged in ENDF/B-VII.1 compared to ENDF/B-VII.0. The major US laboratory contributors to the ENDF/B-VII.1 library are summarized in Table II.Be- 7. Neutron fission yields were reevaluated for 239Pu low we give a summary of the sublibraries. (fast and 14 MeV) by Los Alamos; others were taken over from ENDF/B-VII.0=ENDF/B-VI.8, having been supplied by LANL. TABLE II: Major US laboratory contributors to the ENDF/B-VII.1 library. 8. The thermal neutron scattering sublibrary was car- ried over unchanged from ENDF/B-VII.0. It con- Sublibrary/activity Major US tains thermal scattering-law data, largely supplied contributors by LANL. Neutron sublibrary LANL, BNL, ORNL, LLNL Thermal scattering sublibrary LANL 9. The neutron cross section standards sublibrary was Standards sublibrary NIST, LANL carried over from ENDF/B-VII.0 unchanged [7]. Photonuclear sublibrary LANL Therefore, as for VII.0, the VII.0 standard cross sec- Decay data sublibrary BNL tions were completely adopted by the VII.1 neutron Proton sublibrary LANL 3 reaction sublibrary except for the thermal cross sec- d, t, He sublibraries LANL tion for 235U(n,f) where a slight difference occurs to Fission yield sublibraries LANL satisfy thermal data testing, and some very small Atomic data sublibraries LLNL differences for 235U(n,f) and 238U(n,γ)inthekeV– Data verification BNL Data validation LANL, KAPL, Bettis, ANL, MeV region. INL, BNL 10. The electro-atomic sublibrary was taken over from Archival and dissemination BNL ENDF/B-VII.0=ENDF/B-VI.8. It contains data for 100 materials (all elements) supplied by LLNL.

2892 Cargo screening for nuclear materials Evaluated Gamma Activation File

High energy physics GEANT4 and FLUKA adopt USNDP libraries Capture primary γ’s easy to separate from Geant4 Neutron Data Library background (G4NDL)and difficult based on Most users neverENDF/B-VII.0 see to shield (6-12Thermal MeV) scattering in the ‘High Precision’ neutron models uses ENDF data ENDF/B-VII.0 The radioactive decay data fingerprint forfrom the the Evaluated Nuclear Transport codes such as MCNP, PHITS, ENDF data are most often usedStructure as Data File (ENSDF) FLUKAATLAS detector& GEANT muon system, essential “Neutron for carwash”modeling radiation ADS ATLAS detector muon system, capturing isotope conceptssimulated in Geant4 detector data tables that implement collisionAlso FLUKA uses ENDF/B data simulated in GEANT4 physics in applicationPresence codes of fission products is a clearMike Herman NSAC meeting, Sept. 21, 2012 Wednesday, September 19, 12 indicatorUsers don’t of actinides see them but they can’tbeing live present without (neutrons them! EGAF library allows identification of 104 from spontaneous γ-lines from Pd(nth,γ) fission)

PHITS modelPHITS model of ofJ-PARC J-PARC spallation spallation sourceBrad Sleafordtarget Mike Herman NSAC meeting, Sept. 21, 2012 http://phits.jaea.go.jp/AppsAcSpallationNeutronSource.html

Wednesday, September 19, 12 2

NY Center for Computational Science

SCALE model of INL Supernovae are the site of Advanced Test Reactor r-process nucleosynthesis M. Herman Berkeley, May 27-19, 2015 Overview of structure and reaction databases

ENSDF ENDF/B structure reactions Scope global driven by applications Updating frequent/continuous separate releases Geography world-wide national/regional Source experiment experiment & theory Extrapolation no yes Format ENSDF ENDF-6 Validation n/a extensive

M. Herman Berkeley, May 27-19, 2015 Other popular USNDP products ENSDF: Major Data Sources andEGAF Derivatives Contributing AtomicMasses NlNuclearSSicience Databases: (Wapstra&Audi) References(NSR)

Model Calculations COMMARA-2ENSDF COvariance Multigroup Matrix IE Chart ORTEC & CANBERRA for Advances Reactor Applications

Derivative NUBASE NuDat Empire RADWARE … DtbDatabases:

Derivative Publications: NuBase

M. Herman Berkeley, May 27-19, 2015 ND2013-Sheraton-NYC-3/13 J. K. Tuli ENDF/B-VII.1 Nuclear Data ... NUCLEAR DATA SHEETS M.B. Chadwick et al.

0.08 10 [σ (186W) - σ (182W)] tot tot (n,tot) (n,el) 1/2 [σ (186W) + σ (182W)] (n,inl) tot tot (n,2n) (n,n’) E2+=100 keV (n,n’) E4+=329 keV 0.06 1 (n,g)

s -1 e 10 Cross Section (barns) c 0.04 en r e ff i Nuclear Reaction10-1 Theory 1 10 d Incident Energy (MeV) on

i 0.02 t in Nuclear Data c e s Evaluation 10 ss o 186 r W(n,x)

c 0.00 l a t Experiments 1 o

t never cover

whole energy -1 -0.02 Dietrich 2003 10 Guenther 1982 range and all (shifted - 0.008reaction) channels (n,tot) cross section (barns) -2 (n,el) Soukhovitskii & Capote OMP, 10 (n,inl) (shifted +0.006) (n,2n) (n,3n) -0.04 (n,n’) E2+=123 keV (n,n’) E4+=397 keV 110100 10-3 neutron energy (MeV) 10-2 10-1 1 10 neutron energy (MeV) M. Herman Berkeley, May 27-19, 2015 FIG. 30: Energy dependence of the measured ratio 186 182 186 182 [σtot( W ) − σtot( W )]/ ˘ˆσtot( W )+σtot( W )˜ /2¯ [105] vs. calculated values (blue line) using dispersive coupled- FIG. 31: Neutron induced reactions on 182W(toppanel) channel OMP (RIPL 1480-1482) [109, 110]. and 186W(bottompanel)nuclei:EMPIRE=VII.1calcula- tions (lines) vs experimental data (symbols).

FNG-W benchmark [112] was modeled, which involves a deep penetration of 14 MeV neutrons into a large tung- sten block and is sensitive to tungsten data in the fast neutron energy range. Flux attenuation was measured by a number of activation monitors. The predicted ac- tivity is within two-sigma for all monitors at all depths, without any systematic shifts that increase as a function of the penetration depth, as shown in Fig. 32. The analysis was extended to criticality benchmarks from the ICSBEP Handbook [113], namely the ZPR-9 series of benchmarks from Argonne, and the tungsten- reflected plutonium sphere and the tungsten-reflected uranium assemblies from the Elsie facility at Los Alamos. FIG. 32: Measured activation rates at different depths for the Originally, there was very little improvement in the re- FNG-W experiment [112] compared to calculated values using sults for the criticality benchmarks with the new evalu- the ENDF/B-VII.1 evaluation. ated data. To remedy the situation, a fine-tuning of the model parameters was made (within estimated model pa- rameter uncertainty). Such adjustment had an impact on FNG-W benchmark (see Fig. 32), which would require the calculated capture cross sections below 1 MeV, but adecrease.Sincethereareseveralindependentcritical- had little effect on the previously analysed FNG bench- ity benchmarks using fast-neutron assemblies, which indi- mark. However, there is some contradiction between the cate the same trend, the decision was to retain the higher criticality benchmarks, which would suggest an increase value of the capture cross sections, resulting in about a of the capture cross section below 1 MeV down to about 10% underprediction of the activation of gold at a depth 4keV,andtheactivationmeasurementsforgoldinthe of about 35 cm into the tungsten block as measured in

2920 Nuclear theory ND is a major user and developer of nuclear modeling

Fills gaps in experimental data Extrapolates to ‘no data’ land Provides full set of observables Helps to choose among discrepant measurements Ensures consistency of the evaluation Imposes physical constraints

M. Herman Berkeley, May 27-19, 2015 Room for improvement

ENDF (reaction data) Elimination of compensating errors - targeted differential and semi-integral experiments, and better physics in evaluations Gaps in the ENDF/B neutron sub library No US activation file No US dosimetry library No alpha sub-library in ENDF/B-VII.1 Limited covariances, lack of cross-reaction and cross- material correlations, no covariances for fission product yields No uncertainties for delayed nu-bar Lack of high-energy proton library enabling scoping studies for isotope production

M. Herman Berkeley, May 27-19, 2015 Room for improvement

ENSDF (structure and decay data) Poorly known decay schemes for many medical isotopes and generally for fission products Total lack of covariances Continuous spectra not allowed within current format TAGS data difficult to incorporate in current format Disconnect between structure information and fission yields (i.e. isomeric levels) No theory No information on neutrinos, antineutrinos Evaluation priority not driven by applications

M. Herman Berkeley, May 27-19, 2015