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RADIOLOGICAL SIGNIFICANCE OF THORIUM PROCESSING IN MANUFACTURING . by M.W. Davis Monserco Limited

A research report prepared for the Atomic Energy Control Board Ottawa, Canada

January 1985

1 Canada Research report RADIOLOGICAL SIGNIFICANCE OF THORIUM PROCESSING IN MANUFACTURING

ABSTRACT

The study of thorium processing in manufacturing comprised monitoring programs at a plant where thorium dioxide was in use and another where the use of thorium nitrate had been discontinued. The measurements of the solubility in simulated lung fluid proved that both materials belonged in the Y Class with dissolution half-times greater than 500 days. Bioassay measurements of 20 subjects from both facilities proved that in vitro monitoring methods, urine, feces, hair and nails analysis were not sufficient indicators of thorium uptake. In vivo monitoring by phoswich and large sodium iodide detectors were proven to be good methods of determining thorium lung burdens. The thoron in breath technique was shown to have a lower limit of sensitivity than lung counting, however, due to lack of information regarding the thoron escape rate from the thorium particles in the lungs the method is not as accurate as lung counting. Two subjects at the thorium dioxide facility had lung burdens of 21+ 16 Bq and 29+ 24 Bq Th232 and one at the thorium nitrate facility had a lung burden of .77+ 13 Bq. Improvements in the procedures and use of a glove box were among the recommendations to reduce the inhalation of thorium by workers at the thorium dioxide facility. Decontamination of several rooms at the thorium nitrate facility and sealing of the walls and floors were recommended in order to reduce the escape of thoron gas into the room air. The risk to non Atomic Radiation Workers was primarily due to thoron daughters in air while gamma radiation and thorium in air were less important. Conversely, at the thorium dioxide facility the inhalation of thorium in air was the most significant exposure pathway.

RÉSUMÉ

L'étude sur l'utilisation du thorium dans les usines de fabrication comprenait des programmes de surveillance dans une usine où l'on utilisait du bioxyde de thorium et dans une autre où l'on avait cessé d'utiliser du nitrate de thorium. Les mesures de solubilité dans du fluide pulmonaire simulé ont prouvé que les deux matières appartenaient à la cl ;^so Y et qu'elles mettaient plus de 500 jours pour être à moitié dissoutes. Les relevés pris au cours d'essais biologiques menés auprès de 20 sujets provenant des deux installations ont prouvé que les méthodes de surveillance in vitro et que l'analyse d'urine, des fèces, des cheveux et des ongles ne pouvaient servir d'indicateurs suffisants d'incorporation de thorium. La surveillance in vivo par des scintillateurs «sandwich» (phoswich) et de grands détecteurs à l'iodure de sodium s'est avérée une bonne méthode pour déterminer la charge de thorium dans les poumons. La technique du thoron dans l'haleine a montré qu'elle possédait un seuil de sensibilité inférieur au comptage pulmonaire, mais, a cause du manque de ren- seignements au sujet du taux de fuite du thoron qui s'échappe des particules de thorium dans les poumons, la méthode n'est pas aussi précise que le comptage pulmonaire. Deux des sujets provenant de l'installation de bioxyde de thorium avaient des charges pulmonaires de 21+ 16 Bq et de 29+ 24 Bq Th232 et un des sujets provenant de l'installation de nitrate de thorium avait une charge pulmonaire de 37+ 13 Bq. On a recommandé, entre autres, d'améliorer certaines procédures et d'utiliser une boîte à gants pour réduire l'inhalation de thorium par les travailleurs de l'installation de bioxyde de thorium. On a recommandé de décontaminer plusieurs salles et de sceller les murs et les planchers à l'installation de nitrate de thorium afin de réduire la fuite de thoron dans l'atmosphère des salles. Le risque pour les personnes qui ne sont pas des travailleurs sous rayonnements était dû avant tout à la présence de produits de filiation du thoron dans l'air, mais le niveau de rayonnements gamma et de thorium dans l'air était moins important. Inversement, c'est l'inhalation de i thorium dans l'air qui représentait la voie d'exposition la plus importante à l'installation de bioxyde de thorium. I I I I I I I I I I I

DISCLAIMER

The Atomic Energy Control Board is not responsible for the accuracy of the statements made or opinions expressed in this publication and neither the Board nor the author assumes liability with respect to any loss incurred as a result of the use made of the information contained in this publication. TABLE OF CONTENTS Page

List of Figures V List of Tables vi

1. Introduction 1 1.1 Background 1 1.2 Objective 1 1 1.3 Scope Of Work 1.43 ScopTaskes OTfo WorBe kPerforme d 1 1.5 Summary 1 2 2. Identification Of Quantities And Properties 3 2.1 Background Information From Facility A 3 2.2 Background Information From Facility B 5

3. Review of Radiological Data 6

4. Facility Monitoring 7

4.1 Methods and Calibrations 7 4.1.1 Gamma Exposure Rate Surveys 7 4.1.2 Beta Exposure Rate Surveys 8 4.1.3 Beta-Gamma Exposure Rate Measurements 8 4.1.4 Alpha Contamination Surveys 9 4.1.5 Thoron Gas Measurements 10 4.1.6 Thoron Daughter In Air Measurements 10 4.1.7 Thorium232 Measurements 11 4.1.8 Air Velocity Measurements 11 4.1.9 Alpha Spectrometry - Thorium Age 12 I 4.2 Facility A Results 12 1 4.2.1 Inner Courtyard 12 4.2.2 The Test Lab 13 4.2.3 Storage Room 13 1 4.2.4 (Pre 1970) Thorium Room 14 4.2.5 First Floor Below Present Thorium Room 14 4.2.6 Present Thorium Room 15 1 4.2.7 Mantle Manufacturing 15 4.2.8 Lunch Room and Adjacent Areas 15 4.2.9 Ladies Change Room 16 1 4.2.10 Roof Exhaust - Environmental 16 4.2.11 Contact Beta-Gamma Dose Rate 16 I 4.3 Facility B Results 17 I 4.3.1 ('65-'78) Cnating Room 17 4.3.2 Waste Storage 17 i 4.3.3 Electrode Assembly 17 | 4.3.4 Coating Room 17 4.3.5 Coating Room Exhaust - Environmental 18 4.3.6 Mixing Room 18 ! 4.3.7 Mixing Room Exhaust - Environmental 19 4.3.8 Contact Beta-Gamma Exposure Rates 19 TABLE OF CONTENTS (continued)

i 5. Personnel Monitoring 19 5.1 Methods and Calibrations 20 5.1.1 Whole Body Counting 20 5.1.2 Lung Counting 20 5.1.3 Thoron In Breath 21 1 5.1.4 Urinalysis 22 5.1.5 Fecal Analysis 22 5.1.6 Hair and Nails Analysis 22 5.2 Facility A Results 22 I 5.2.1 Whole Body Counting 22 5.2.2 Lung Counting 23 5.2.3 Thoron In Breath 23 I 5.2.4 Urinalysis ' 23 5.2.5 Fecal Analysis 24 5.2.6 Hair and Nails Analysis 24

I 5.3 Facility B Results 24 5.3.1 Whole Body Counting 24 5.3.2 Lung Counting 24 I 5.3.3 Thoron In Breath 25 5.3.4 Urinalysis 25 5.3.5 Fecal Analysis 25 5.3.6 Hair and Nails Analysis 25

| 6. Solubility in Simulated Lung Fluid 25

7. Evaluation of Radiological Significance and Recommendations 26 I 8. Conclusions 30 I 9. References 31 I Figures

I Tables

Bibliography LI5T OF FIGURES

FIGURE TITLE 4.1-1 Calibration Curve of Sodium Iodide Detector 4.1-2 Calibration Curve of Sodium Iodide Detector (Detail) 4.1-3 Panasonic UD801 Thermoluminescent Dosimeter 4.1-4 Epidermal Thickness of Fingers and TLD Filtration 4.1-5 Anemometer Calibration - High Range 4.1-6 Anemometer Calibration - Low Range 4.1-7 Th228/Th232 Activity Ratio After Separation 4.1-8 Relative Activities in Thorium Dioxide Facility B

4.2-1 General Layout of Facility A 4.2-2 Layout in Vicinity of Thorium Room - Facility A 4.2-3 Inner Courtyard - Facility A 4.2-4 Test Laboratory - Facility A : Occupational Monitoring 4.2-5 Storage Room - Facility A : Occupational Monitoring

7-1 Fraction of Annual Dose Limit for Non Atomic Radiation Workers at Facility A 7-2 Th232 Pathways from Soil to Man -vi-

LIST OF TABLES

TABLE TITLE 2-1 Job Description / Work Histories Facility A 2-2 Job Description / Work Histories Facility B 2-3 Thorium Dioxide Usage at Facility B since 1966

3-1 Thorium Decay Chain

4.2-1 Thorium Room Exhaust Stacks - Facility A 4.2-2 Contact Beta-Gamma Exposure Rates on Mantles 4.2-3 Contact Beta-Gamma Exposure Rates on Thorium Metal

5.2-1 Summary of Bioassay Results of Facility A Subjects 5.2-2 Thoron in Breath Results - Facility A 5.2-3 March Urinalysis Results - Facility A 5.2-4 August Urinalysis Results - Facility A 5.2-5 March Feces Results - Facility A 5.2-6 Th232 in Hair and Nails - Facility A

5.3-.\ Summary of Bioassay Results of Facility B Subjects 5.3-2 Thoron in Breath Results - Facility B 5.3-3 March Urinalysis Results - Facility B 5.3-4 August Urinalysis Results - Facility B 5.3-5 March Feces Results - Facility B 5.3-6 Th232 in Hair and Nails - Facility B

6-1 Composition of Simulated Lung Fluid 6-2 Solubility of Thorium Dioxide from Facility B in Simulated Lung Fluid 6-3 Solubility of Th232 in Simulated Lung Fluid 6-4 Solubility of Ra221* in Simulated Lung Fluid

7-1 Factors Used in Pathway Analysis Calculations I 1.0 INTRODUCTION This report summarizes the work carried out during the study for the Atomic Energy Control Board (AECB) titled 'The Radiological I Significance of Thorium Processing in Manufacturing1. i 1.1 Background Thorium compounds, mainly in the form of powders, are used in the manufacture of numerous commercial products such as optical I glass, gas mantles, tungsten v/elding electrodes, electrical filaments and in various metal alloys. Many of these compounds can be inhaled resulting in radiological insult to workers and, when released to the I environment, to the public.

I 1.2 Objective The objective of the study is to assess the radiological signifi- cance of radionuclides associated with thorium processing in the I manufacture of industrially and commercially used devices in Canada.

1.3 Scope Of Work

The scope of work includes an identification of the dosimetrically significant physical and chemical properties of thorium compounds handled and produced in Canadian industry. An assessment of the radiological significance of radionuclides associated with thorium processing will follow by means of: a) a review of available information; b) monitoring in the workplace of the levels of radionuclides associ- ated with thorium processing in manufacturing; c) a program of in vitro and in vivo measurements (urinalysis, body burden, thoron in breath) of workers handling these compounds; and d) a study of the solubility in simulated lung fluid of the thorium compounds handled and stack emissions from the manufacturing plant.

1.4 Tasks To Be Performed

The tasks to be performed include: a) identify the thorium compounds processed, the quantities handled, and thorium by-products in stack emissions in the manufacture of industrially and commercially used devices in Canada; i - 2 -

b) describe the physical and chemical properties of the radioactive compounds associated with the thorium processing; ( c) assess the radiological significance of these compounds by: i) a review of available information ii) monitoring of the levels of the radioactive compounds in the ( workplace and outside (where there are stack emissions) iii) carrying out a program of in vitro and in vivo measurements for workers if warranted by ii) above (as determined by the Scientific Authority of the AECB) ( iv) carrying out a study of the solubility in simulated lung fluid of the thorium compounds handled and in stack emissions; and v) relating the information obtained in i), ii) and iii) to the radiological significance for workers and the public by the use I of existing metabolic and dosirnetric models for radio-compound uptakes, and environmental pathway analysis. I 1.5 Summary I The study of tnorium processing in manufacturing comprised moni- toring programs at one plant where thorium dioxide was used and at (another where there were residual effects after the use of thorium nitrate had been discontinued.

Solubility in simulated lung fluid measurements were made using materials from both facilities. The results placed both the thorium dioxide and the thorium nitrate in the Y Class with solubility half-times greater than 500 days. Although the thorium nitrate was highly scluble in the nitrate form, immediately after going into solution the thorium formed an insoluble complex in the simulated lung fluid.

Bioassay measurements of a total of 20 subjects from the two facili- ties illustrated that in vitro monitoring methods, urine, fecal, hair and I nails analysis were not sufficiently sensitive indicators of thorium uptake. Lung burdens were measured in three subjects at 21+ 16 Bq, I 29+ 24 Bq and 37+_ 13 Bq by in vivo methods using phoswich and large I so"3ium iodide detectors. Lung burdens were detected with a lower limit of sensitivity by the thoron in breath technique than by lung I counting. However, due to uncertainty about the thoron escape rate from thorium particles in the lungs, the thoron in breath technique cannot be used to accurately calculate lung burdens with the limited amount of information available. * Extensive monitoring of the occupational and surrounding environ- ment was carried out at the two plants. Gamma and beta exposure (rates were measured, thoron, thoron daughters and Th232 were analysed in air using open face and respirable air samplers. Th232 was measured in soil, concrete and roofing material, total and remov- able alpha contamination was measured and air velocities and flow rates were measured. Some aspects of the radiological significance of the I findings were distinctly different at the two plants. At Facility A the risk to non Atomic Radiation Workers was primarily due to thoron I daughters in air while gamma radiation and Th232 in air were less important. On the other hand, at Facility B the inhalation of Th232 is I - 3 -

the significant exposure pathway. Recommendations regarding the immediate remedial action to be taken at Facility A centered on decontaminating three of the most highly contaminated areas and seal- I ing the walls and floors to decrease the escape of tlioron gas into the room air. in the longer term when renovations are made or the prop- erty is sold, it will be necessary to breakup and dispose of the thor- t ium impregnated concrete, soil and roofing material in approved sites. Recommendations regarding 'mprovements in procedures and equipment were made to reduce the inhalation of thorium by the workers at Facil- I ity B. Until it has been demonstrated that thorium uptakes have been reduced it is recommended that semi-annual lung counting and thoron in breath measurements be made on each subject working in the mixing J and coating rooms. Contact beta-gamma exposure rate measurements were made using thermoluminescent dosimeters (TLDs) held against two types of lantern mantles, pieces of thorium metal and electrodes onto which thorium had been mechanically fixed. Appropriate filtration was used so that the results were applicable to finger and hand exposures with and without i cotton gloves. The contact exposure rates ranged from 3.5 to 4.8 mR/h for the mantles, 17.3 to 30 mR/h for the thorium metal and 0.23 to 0.63 mR/h for the electrodes.

2.0 IDENTIFICATION OF QUANTITIES AND PROPERTIES

I At both facilities under study relevant information concerning all aspects of the use of thorium was collected. I 2.1 Background Information From Facility A

Thorium was used in manufacturing at Facility A between 1947 and I 1983. The stock material is thorium nitrate { ThCNOj^^H-O} which is a colourless crystalline material with molecular weight of 552.12. It is I very soluble in hot or cold water and alcohol and is slightly soluble in » acetone. Thorium has been purchased from May & Baker Canada Inc. since the late l?7CCs. Fifty kilogram lots of the stock material were I packaged in double polyethylene bags with sealed tops ana shipped in steel drums. The drum lid was secured with a hoop. The thorium usage rate during recent years is reported to have been :

Year kg Per Year

1977 33,7UU 1980 11,930 1981 16,930 1982 9,780 1983 2,370

As manufacturing demanded, thorium powder was removed from the storage room to the wet process area where it was dissolved in water. The mantle materials were soaked for about an hour in the thorium solution and then eentrifuyed to remove the excess. The materials were then spread on racks and air dried for about an hour in ovens. Then the materials were transferred to a cabinet and exposed to anhydrous ammonia to convert the thorium nitrate to the oxide form. The materials were washed and rinsed to remove excess ammonia and then they were centrifuged and huny on racks to dry. In order to stiffen the materials a lacquer was applied and dried.

In the dry processing area, the thorium laden materials were sewn, clipped, stamped with the manufacturers name and a hardening solution was applied to one end of the product. Until 1979 the harden- ing solution contained thorium, but it has not been an ingredient of the hardening solution since that time. Finally, the mantles were stacked on wooden trays to dry.

I Stock thorium nitrate was stored in a small metal shed located external to the main manufacturing building on the ground floor. Controlled access was through an exterior door. Ventilation was not provided for this area. The inventory fluctuated with use and delivery of stock with a normal maximum of 30 drums. Until about 1971) the wet and dry process areas were on the main floor of the manufacturing building. After 197Û the two processes were moved to the two second floor rooms that were in use until thorium processing was discontinued in 1983. Solid thorium bearing waste was disposed of with normal garbage or burned on the premises until 1981. Solid thorium waste generated since that time was held in steel drums and then disposed of at the Radwaste Disposal site at Chalk River.

Thorium bearing liquid waste resulted from normal cleaning of the manufacturing areas and the process itself. Machines in the dry I process area were steam cleaned once per week and the floor in the wet process area was washed each night. All waste water was drained directly to the city sewers. Process solutions also passed directly to the city sewers from the centrifuge, washer, sink and four floor I drains in the wet process area. Exhaust air from the drying ovens, denitriding and lacquering cabinets is vented directly to the roof. Exhaust air from the process- ( ing area is also vented directly to roof exhaust stacks.

AECB and company files show that external dosimetry and urinaly- sis records were maintained for workers in the early 1970's. Between i 1973 and 1979 both monitoring methods appear to have been discontin- ued. In 1979 external dosimetry and urinalysis monitoring were reinstated and recently (since 1980) thorax burden measurements have been made by the Radiation Protection Bureau in Ottawa. For those subjects who participated in this study, work histories are given in Table 2-1.

I - b -

2.2 background Information From Facility B

Thorium in both metallic and oxide forms has been in use at Facil-

ity D since at least 1966. The thorium dioxide {ThO2, molecular weight 264.02} comprises fine white crystals and is insoluble in water, dilute acid and alkaline solutions. [t is soluble in hot sulphuric acid. Thorium dioxide stock material is currently supplied by May & Baker Canada Inc. in 1Û kg lots sealed in a polyethylene bag in a small drum. The drum lids are secured with a hoop.

The thorium metal is procured in sheets 0.076 mm thick and is cut on site into pieces 2.5 x 0.25 mm and weighing 0.5 mg. Thorium metal has a molecular weight of 232.038 and a density of 11.7 g/cm3 . It is insoluble in water and only slightly soluble in nitric acid. It is soluble in hydrochloric and sulphuric acids.

Eleven subjects, who have worked with thorium at Facility B dur- ing some time since 1966, volunteered to participate in the study. Their job descriptions and work histories are summarized in Table 2-2.

Complete and reliable records of thorium dioxide preparation have been kept by subject B7 since 1966. The annual rate of thorium usage i has been taken from those records and is reproduced in Table 2-3. Current handling of thorium takes place in four locations; the mixing room, the coating room, the manufacturing area and the storage I room. Thorium dioxide stock material is stored in a glove box in the mixing room and as production demands it is prepared in solution currently about once every two months. The solution is a mechanical I mixture of thorium dioxide and bicarbonates in methanol. The mixture is crushed in a ball mill and then transferred into polyethylene bottles for storage. The solution is stored in the mixing room until required I and the bottles are rolled continously to maintain the mix. In the coating room the thorium is mechanically fixed onto electrodes on a daily basis. Thorium/methanoi mixture from a stock of ( a few litres kept in the coating room is poured into small trays and the electrodes are immersed in the liquid. The trays are transferred into I a vacuum chamber and the air pressure is reduced to about 5 cm of mercury to release trapped air. After the air pressure has been raised to normal the trays are transferred to a water bath where the methanot is evaporated leaving dry thorium dioxide and coated I electrodes. The electrodes are transferred to a clean tray after the e\cess thorium is shaken off. Instructions require that coating room operators wear rubber gloves, use the fume hood for most tasks and I no smoking or eating is allowed. In the manufacturing area the electrodes are fired in a hydrogen I furnace to fix the thorium before use. The final assembly stage involves two steps: a) the electrodes covered with thorium are handled individually with tweezers and are welded to a second cornpon- ent, b) the welded components are sealed inside the final assembly by I a second worker. I - 6 -

The present coating room has been in use since 1978. From about 1965 until 1978, the coating room was located on a lower floor.

All solid thorium waste materials are presently collected and stored separately in specially designated barrels. These barrels are held in the area set aside for storing hazardous solvents and reagents.

The thorium metal sheets received from the supplier are about 4 cm on a side and are 0.076 mm thick. Once per month the sheets are cut into narrow strips and cleaned by electrolysis. After cleaning they are cut into 0.5 mg pieces and are stored in a nitrogen atmos- phere until required. Instructions require that the thorium be handled by tweezers or with cotton gloves.

The air drawn from the mixing room and the fume hoods therein have a common exhaust on the north wall of the building. Air is drawn into the room around the door by the negative pressure gener- ated by the exhaust fans.

In the coating room there is a supply of fresh air provided which greatly exceeds the exhaust drawn from the room through the hooded box in which the dry thorium powder is handled. Therefore, some of the coating room air is expelled through the doorway into the manufac- Ï turing area by the positive pressure created inside the room. An exhaust fan draws air through a filter from the hood in the coating room and exhausts it through a roof vent which is part of an adjacent ventilation system.

I 3.0 REVIEW OF RADIOLOGICAL DATA A literature survey was conducted using the International Nuclear Information System (INIS) which was accessed via the National I Research Councils CAN/OLE database system. INIS is maintained and updated by the International Atomic Energy Agency and covers all I peaceful applications of atomic energy. The database contains reports covering the period 1970 to the present. Abstracts and publication data of the reports dealing with occupa- tional, environmental, monitoring and dosimetric aspects of thorium and its daughters are included in the bibliography.

No references addressing the solubility of thorium or its compounds in simulated lung fluid were found. Several additional reports relating to the studies of thorotrast patients were identified.

Rundo (Ru78) has published a review of the radioactive properties and biological behaviour of thorium232 and its daughters. The thorium decay chain, Figure 3-1, comprises isotopes of eight different chemical elements, three are represented twice. As a result of nuclear trans- formations, the chemical identity of the radioisotopes changes. When these radioisotopes are located inside living organisms, the new chemi- cal species may be incompatible with the site environment. - 7 -

The uptake of thorium dioxide by inhalation and injection into beagle doys was studied by Ballou and Hursh (Ba72). The dust was enriched in Th228 to enhance thoron production and measurement sensitivity. Airborne dust concentrations averaged 18d mg/m3 with a particle size distribution of 0.11 [im CMD (count median diameter- median diameter based on number of particles) aq 2.13 and 1.75 p.m AMMD (aerodynamic mass median diameter) ag 2.86. Immediately after

inhalation the dust burdens averaged 2.12 mg ThO2; but only an average of 0.27 mg was located in the lower respiratory tract. The thoron/Th228 ratio in lung varied from 0.10 to 0.17 during the interval from 3 to 150 days following inhalation; indicating a steady-state relationship was quickly established. Higher values have been report-

ed for human thorotra^t patients, however, the ThO2 particles were much smaller at 75 A CMD for thorotrast compared to 2000 A in Ballou's work. Ballou also measured a biological half time in the lungs of 350 - 500 days which agrees well with the ICRP Task Group on Lung Dynam- ics recommendations.

Recently Newton (Ne8l) reported a case where a male became internally contaminated with Th228, presumably through inhalation of the oxide. A seven year study of this subject resulted in the conclu- sion that the biological half-life for long term clearance from the body was at least 14 years and probably longer. Also, it was concluded that the material had cleared the lung as a Class W compound. However, this was not observed directly since the detection of the burden and subsequent monitoring took place after the lungs had been cleared.

4.0 FACILITY MONITORING

4.1 Methods And Calibrations

4.1.1 Gamma Exposure Rate Surveys

Gamma exposure rate measurements were made using a 2" x 2" sodium iodide detector and RASCAL PRS-2 sealer (s/n 247). Radiation levels as low as 0.5 |j.R/h can be measured with an accuracy of +10% and -3O5IÏ; 300 counts in a 30 second counting interval.

The energy and exposure rate responses of the detector system were determined using Cs13\ Co60 and Ra226 calibration sources. Accumulated counts in 30 seconds at a true exposure rate of 8 mR/h from Cs13l) (0.605, 0.794 MeV), Co60 (1.17, 1.33 MeV), and Ra226 (.187 MeV plus others) were 967,000; 759,000 and 746,000 respective- ly. The Ra226 calibration factor was used to calculate exposure rates in this study. Therefore, the exposure rate can be overestimated by up to 30% as the energy of the radiation varies. The radiation fields around the Cs134 and Co60 sources were calibrated using a Farmer Dosimeter which itself has a calibration that is traceable to National Research Council standards. The Ra226 source was calibrated using an ion chamber and sources traceable to the United States National Bureau of Standards (NBS) (Ha84). - 8 - I The exposure rate response of the detector was checked between 60 and 8000 |iR/h usiny the Ra226 source. The calibration curve is I plotted in Figure 4.1-1 and the non-linearity due to dead-time losses is apparent above 25U ^R/h. The calibration curve detail below 250 (iR/h is replotted in Figure 4.1-2. The calibration curve was forced to pass through the origin and the slope was calculated by least square fitting 1 to the three data points shown. In the range 0 - 251) |iR/h, tne gamma exposure rate, ER p.R/h, is calculated using the equation:

ER = CR x 0.00159

where CR = counts per 30 seconds 0.00159 = calibration factor in p-R/h per count per 30 seconds

4.1.2 Beta Exposure Rate Surveys

Beta exposure rates were measured using an AEP 2153B monitor of Atomic Energy Canada Limited (AECL) design. The thin end window geiger tube has a removable steel window in front and can be used to measure beta exposure rates in the range 0 - 100 mR/h. In the presence of gamma radiation, the beta exposure rate is the difference between the two readings with the steel window open and closed.

Calibration of the monitor had previously been carried out using a P32 source. The absolute value of the activity of the source was determined by 4 pi beta counting. The accuracy of the beta dose rate was estimated to be +50% (st84).

4.1.3 Beta-Gamma Exposure Rate f\/leasurements

Extremity exposure rates for workers handling radioactive materials in the two facilities were measured using thermoluminescent dosimeters (TLDs). Various objects were placed in contact with the TLD for a recorded exposure interval. The lithium borate element No. 1 of the UD801 TLD manufactured by Panasonic was used for this study (see Figure 4.1-3). The elements of all plaques had been individually calibrated in the radiation field around a Co6C source. A Farmer Dosimeter (calibration traceable to the NRC) had been used to measure the exposure rate around the Co60 source.

The filtration over the lithium borate chip was determined after reference to the skin thickness of the hand reported in "Report of the Task Group on Reference Man1 (ICRP23). From the table in that report which lists the thickness of the epidermis for six main body site groups for males and females ages 15 - 89 years it was noted that the thickness for the fingers and fingertips was 220 and 370 \im respec- tively. The standard deviation was also reported to be 120 and 112 \im respectively. Based on a tissue density of 1.1 g/cin3, these values were converted to equivalent mg/cm2 and are shown in Figure 4.1-4. The filtration levels of 19 and 27 mg/cm2 used in these measurements - 9 -

are shown bracketing the thinnest epidermal region exposed when a radioactive item is picked up in the fingers.

I It is appropriate to note at this point, that the most energetic alpha particles emitted by the thorium232 series, 8.79 MeV (Po2*6), cannot penetrate the epidermis layer on the fingers and therefore are I not considered an exposure hazard. The maximum range of an 8.79 MeV alpha particle in tissue can be calculated using equations I from 'Introduction to Health Physics' (Ce76).

4.1.4 Alpha Contamination Surveys

i Total and removable alpha contamination levels were determined by different methods, direct instrument measurement and wipe counting respectively. Total alpha contamination was measured on flat surfaces I using a zinc sulphide scintillation detector (model 702 'Poppy' probe) and Thyac III ratemeter manufactured by Victoreen. The ratemeter has four ranges xl, xlO, xlOO and xlOOO and the scale on the meter I covers 0 to 800 counts per minute. Calibration of the detector system was made using a standard I source with a known alpha flux and traceable to the US NBS. The counts per minute observed on the meter were converted to I radioactivity densities by making the following calculation:

A = 2 x C / (0.286 x 1.27)

| where A = alpha activity density, dpm/100 cm2 C = count rate observed on the meter, cpm

0.286 = detector efficiency relative to the 2 pi alpha flux emitted by the standard cpm per alpha/minute

2 = factor to convert 2 pi alpha flux to 4 pi alpha disintegration rate

1.27 = the ratio of the area (127 cm2) of the detector face to 100 cm2

I The minimum sensitivity is 50 cpm using the lowest range. Since the area of the detector face is 127 cm2, the minimum sensitivity corresponds to an alpha activity density of 280 dpm/100 cm2 .

Wipes taken to determine removable contamination were measured using a windowless gas flow proportional counter. The counter effi- ciency is checked regularly using the alpha calibration source indicated above. For the purposes of calculating the removable contamination on the surface wiped, it was assumed that only 10% of I the activity stuck to the wipe and was counted. The background in the proportional counter is 0.5 cpm and the efficiency is 100% (not I - 10 -

including the geometry factor). The minimum sensitivity of the system I for a 2 minute count is 1 dpm on die wipe and 10 dpm/10U an2 when the wipe has been dragged over 100 cm2 . I 4.1.5 Thoron Gas Measurements The concentration of thoron gas in air was measured using the two I filter method described in the 'Manual on Radiological Safety in Uranium and Thorium Mines and Mills' (Ss43). A steel tube of inner length and diameter 50 cm by 5 cm respectively was fitted with 0.8 am pore size membrane filters at each end. Air was drawn through at a rate of ( 10 +5% L/min and the flow was held constant by the use of a critical orifice. Between 7 and 24 hours after sample collection, the filters were alpha counted on the windowless gas flow proportional counter ( described above. The fraction of thoron decay atoms in the tube that deposit on the exit filter was calculated to be 0.664 using the approp- riate equation from Appendix III (Ss43).

4.1.6 Thoron Daughter In Air Measurements

Thoron daughter concentrations in air were measured by drawing an air sample through a filter and measuring the alpha activity of the Pb212(Bi212) daughters in a windowless gas flow proportional counter. Total thoron daughter concentrations were measured in large air samples using an open face filter and sampling flow rates in the range from 10 to 30 L/min. Respirable thoron daughter concentrations in smail air samples were measured using a flow rate of 1.7 L/min through I a 10 mm nylon cyclone separator and a down-stream in-line filter. Membrane filters with 0.8 urn pore size were used in both cases.

I The open face filter system consisted of the aluminum filter holder, a critical orifice to hold the flow constant at 10 or 14 L/min and a diaphragm air pump (GAST model DOL-101-AA). In a few cases, no I critical orifice was used and the sampling flow rate varied from 33 to 27 L/min as the filter loaded up. During sample collection, the plane of the filter face was oriented perpendicular to the ground. If there was a significant flow of air, as in an exhaust duct, the plane of the filter face was also oriented parallel to the air flow. The respirable size aerosol sampling system included a DuPont model 2500 personnel air sampling pump with self regulating flow and nylon cyclone separator and in-line filter described above. I The flow rates of both systems were calibrated using a bubble tube and stop watch. The uncertainty in the calibration of the flow rate is estimated to be no greater than +b%. I Alpha counting of the membrane filters was carried out on the windowless gas flow proportional counter described in Section 4.1.4. The minimum sensitivity of the method based on a 2 minute counting I interval is 0.017 Bq. I ï - 11 - 4.1.7 Thorium232 Measurements

Thorium232 concentrations in air, soil and construction materials were ineasured by alpha counting or by neutron activation analysis.

Thorium232 concentrations in air were determined for total f particulate and respirable particulate species. The air sampling meth- ods have been described in the section on thoron daughter measure- ments and many of the same filters were used for both analyses. The 1 amount of thorium232 on each filter was determined by the neutron activation method. After air sample collection, the filter was prepared for neutron irradiation with thorium standards prepared on filter papers. Counting of the activated samples and standards took place a i few days after irradiation to allow short-lived interfering activities to decay.

The thermal neutron irradiation of Th232 produces Th233 which quickly decays (half-life 22.2 minutes) to Pa233. Protoactinium233 has a half-life of 27 days and decays by the emission of a beta particle and numerous gamma rays including one at 312 keV. A hyperpure german- ium detector was used to count the samples and standards using the 312 keV photopeak.

I Thorium standards used in determining thorium on filter papers were prepared by pipetting commercially available atomic absorption standards onto blank filter papers. Sediment rock standards STSD-2 1 from the Canada Center for Mineral and Energy Technology (CANMET) and standard rock GSP-1 from the United States Geological Survey were used as standards for the determination of thorium in soils and I roofing materials. Thorium232 was also measured on some of the filters by alpha counting in the windowless gas flow proportional counter after the I thoror daughter activity had decayed. The calculation of Th232 cont- ent was based upon the results of thoron retention and equilibrium measurements made with the alpha spectrometer and described in I Section 4.1.9.

4.1.8 Air Velocity Measurements

Air velocity measurements in the labs, vents and air ducts were made using a Datametrics 100VT Air Flow Meter (s/n 2486) manufac- tured by Dresser Industries. The meter has two ranges, 0 - 600 feet per minute (FPM) and 600 - 6000 FPM and operates on the hot wire anemometer principle. The probe has a diameter of 9.5 mm and a length of 197 mm. It is connected to the control box by 2.3 m cable and can easily be manipulated into small openings.

The meter was calibrated on the upper range using an automobile speedometer which had been calibrated against Ontario highway kilometer markers. The lower range was calibrated using a uniformly i rotating wheel and stopwatch. The calibration curves are shown in Figures 4.1-5 and 4.1-6 respectively. I - 12 -

4.1.9 Alpha Spectrometry - Age Of Thorium Stock Material»

The interval since refining of the thorium and the retained fraction of thoron gas in the thorium dioxide particles were measured by alpha spectrometry. A thin source was prepared, with no chemical treatment, and a surface barrier detector and multichannel analyser were used to determine the alpha spectrum.

I A sample of thorium nitrate, similar to the stock material used at Facility A, was obtained by AECL Chalk River from May & Baker Canada Inc. and the alpha spectrum was measured. The alpha activity I ratios were determined to be: Th230/Th232 = 0.18 +0.04 Th228/Th232 = 0.43 70.05

I and the daughters of Th228 were in equilibrium (jo84). The age of thorium since refinement and radium separation was estimated to be between 3 and 8 years. This estimate was based upon the variation of I Th228/Th232 activity ratio shown in Figure 4.1-7.

A sample of thorium dioxide, taken from stock material used at Facility B, was analysed in a similar manner. The alpha activity ratio I was determined to be: I Th228/Th232 =0.60+0.045 Based on the activity ratio curve shown in Figure 4.1-7, the age of the thorium from Facility B is either 1.4 to 2.0 years or 10.5 to 13 years. Since the function is double valued it is impossible to determine which age range is correct based on only one measurement. The relative alpha count rates of the Th228 daughters are shown in Figure 4.1-8. Within the uncertainties indicated due to counting statistics all the Th228 daughters are in equilibrium.

It is significant to note that the Rn220 has been almost completely retained within the thorium dioxide particles. It is estimated that the escaping fraction of Rn220 is less than 2%.

4.2 Facility A Results

4.2.1 Inner Courtyard

In the past waste mantle material was burned in the inner court- yard shown in detail in Figure 4.2-3. The location of the courtyard within the plant is shown in Figure 4.2-1. Gamma exposure rates were measured at an elevation of one metre above the ground/asphalt using the Nal/ RASCAL system and the results are shown in Figure 4.2-3. In general the exposure rate above the asphalt surface is about 4 (iR/h except near the center where elevated levels of 13 and 7.9 (aR/h indi- cate the remains of thorium laden waste. The other two sections of the courtyard are bare soil and the corresponding exposure rates are higher, 6 to 7 |j.R/h due to lack of asphalt shielding. I 4.2.4 (Pre 197U) Thorium Room

I The dissolution of the thorium nitrate used to take place near the east wall of this room. Gamma radiation fields of 150 jiR/h were meas- ured at the wall one metre above the floor. The field decreased rapid- I ly to 22 nR/h at a distance of 2 metres from the wall. The thoron • daughter concentrations in air were calculated to be 4.6 Bq/m3 (±9%) and 4.2 Bq/m3 (+33%). Air volumes of 4.6 and 0.20 m3 were pulled through an open face filter and the respirable air sampling system ( respectively. Th232 concentrations in air were determined to be <.04 and <.02 using the same filters (NAA). The removable alpha contamination levels in this area were found to range from <10 to ( 430 ppm/100 cm2. Except one wipe, which indicated a contamination level of 9900 dptn/100 cm on the wall one metre above the floor where the mixing took place. I On the other side of the wall, to the east of the (pre 1970) thor- ium room, the gamma fields are 34 nR/h at the wall over the drain. The open drain stretches for a distance of about 11 metres and gamma radiation above it is fairly constant at about 30 |iR/h. Thoron daugh- I ter concentrations in air over the drain were measured on three occasions using open face filters. The results were 4.8, 1.1 and I 0.57 Bq/m3. Tn232 was measured at <0.02 ^ig/m3 on each filter. 4.2.5 First Floor Below Present Thorium Room

I On the first floor below the present thorium room three different areas were designated, the east room, the south room and the machine I shop (directly below the thorium room), see Figure 4.2-2. The gamma radiation fields in the machine shop ranged from 14 to 45 (iR/h with an average of 25 [iR/h. The thoron daughter concentra- I tion in air was measured with an open face filter and respirable air sampler. The results were calculated to be 7.0 (±5%), 10.2 (±6«) and 6.4 (±5%) Bq/m3. The Th232 on each of these filters indicated < .04 Bq/m3. Five floor wipes indicated 30 to 90 dpm/100 cm2 remov- able alpha contamination. Higher levels up to 1000 dpm/100 cm2 were found on top of cabinets and ductwork using 5 additional wipes.

The gamma radiation fields in the east room were a maximum of 14 p.R/h at the wall below the thorium room and decreased to normal background within a few metres. An 8.3 m air sample was taken with an open face filter and the thoron daughter concentration in air was calculated to be 1.4 Bq/m3 ±7%. The Th232 concentration in air was < .02 3

A 6.2 m3 air sample was used to determine the thoron daughter I concentration in air in the south room. It was calculated to be 0.75 Bq/m3 ±55K. The Th232 concentration was 0.006 (±28%) Bq/m3. - 15 -

4.2.6 Present Thorium Room

Thoron daughter concentrations in air were measured on 7 occasions using open face filters. The results ranged from 5.8 to 34 Bg/m3 with an average of 16.9 Bq/m3. The highest values were observed in the winter at 23 and 34 Bg/m3 and the lowest values, 9.3 1 and 15.7 Bq/m3 after the new thorium room exhaust fans had been installed and operated in the fall.

| Th232 concentrations in air were also measured using 6 of the open face filters; results ranged from <0.1 to 11.23 ng/rn3 with an average of 0.13 ng/m3. Once again the highest values were observed in the win- ter. The results of the respirable air samples taken in the fall were 1 <0.113 and <0.06 ng/rn3

The average gamma radiation exposure rate in the thorium room is 50 fjR/h. Jn the corner where the thorium nitrate used to be dissolved the exposure rate increases to 200

The removable alpha contamination was measured using 10 wipes and the results ranged from 90 to 1700 dpm/100 cm2. The five floor wipes indicated 90 to 870 dpm/100 cm2. The remaining 5 wipes of shelves and the oven top etc. were generally higher. The 1700 dpm/ 100 cm2 value was found on the lower shelf of the bench where thorium solutions were prepared.

4.2.7 Mantle Manufacturing

In the mantle manufacturing area the thoron daughter concentra- tions in air were measured in the winter using open face filters and they were calculated to be 6.3 Bq/m3 (±13») and 7.1 Bq/m3 (±11%). Two other measurements were made in the fall after the new exhaust system had been installed in the thorium room. The thoron daughter concentrations in air were calculated to be 5.8 Bq/m3 (±1035) using the radon tube and 8.3 Bq/m3 (±20%) using the cyclone separator and personal sampler.

Th232 was measured by NAA on two of the same air filters and the concentration in air was calculated to be <0.082 (ig/m3 using the radon tube and <0.097 ng/m3 using the cyclone separator and the personal air sampler.

Gamma radiation fields were found to average 15 (iR/h except near wooden trays etc. that had been used to stack thorium laden materials. In these areas the exposure rate increased to 50 |J.R/h.

4.2.8 Lunch Room And Adjacent Areas

The results of the gamma survey of the lunch room indicate that natural background radiation fields of 4 to 6 |iR/h prevail throughout. In the adjacent manufacturing areas the gamma radiation fields at the walkway beside the mantle manufacturing area were 9.7 nR/h but - 16 -

decreased to natural background a few metres from the walkway.

The thoron daughter concentrations in air were measured in the lunch room and adjacent manufacturing area using open face filters. There was very little difference in the results in winter and fall; the average of the five values was 4.7 Bq/m3 with a standard deviation of 0.63 Bq/m3.

4.2.9 Ladies Change Room

The gamma radiation fields were generally 8 |iR/h and increased to 12 nR/h at the wall adjacent to the thorium room.

In the ladies change room eight measurements of thoron daughter concentrations averaged 11.5 Bq/m3 with a standard deviation of 3.9 Bq/rn3. These represent five open face filter samples and three samples of respirable size particles.

Th232 concentrations in air were measured three times with open face filters, <0.125, <0.08 and <0.10 (ig/m3, and once with the cyclone separator, <.147 (ig/m3.

The removable alpha contamination was measured using 5 wipes and the results ranged from 10 to 150 dpm/100 cm2.

4.2.10 Roof Exhaust - Environmental

The air flow rates out of the thorium room exhaust stacks were measured with the hot wire flow meter. The air speeds, duct sizes, etc. are given in Table 4.2-1. The volume of the thorium room is 465 m3 and the air change rate varies from 18 to 23 per hour when the room is occupied and the cabinet exhausts are on.

The thoron daughter concentrations in roof exhaust air was meas- ured at each of the dryer, lacquer, and ammonia cabinet exhausts and the old and new exhaust systems from the thorium room itself. The concentrations ranged from 9.0 to 13.2 Bq/m3 and were very similar to thorium room values. This is to be expected since the exhausts are unfiltered.

4.2.11 Contact Beta-Gamma Exposure Rate

The contact beta-gamma exposure rates were measured with TLDs on two types cf lantern mantles. The results are shown in Table 4.2-2. In a 2000 hour working year the maximum dose to the fingers could be as high as 9600 mRad. I - 17 - I 4.3 Facility B Results

Thoron daughter concentrations in air wnre measured in the mix- ing, coating and storage rooms and all results were <1 Bq/rn3.

4.3.1 ('65-'78) Coating Room

The gamma radiation fields in this area were as high as 15 nR/h in one spot but generally were at the background level of 5

Total alpha contamination levels on the floor were less than 280 d^m/100 cm2 in all areas including where the varathane floor covering had been worn away to expose the bare concrete. Removable alpha contamination was non-detectable on all four wipes and therefore is lass than 10 dpm/100 cm2.

4.3.2 Waste Storage

Gamma fields in the waste storage area were generally at the natural background level except in the vicinity of the 45 gallon drums I of waste. Contact radiation readings varied up to 0.5 mR/h. Th232 concentration in air was below the detection limits on 3 different days at <.O6, < .06 and < .16 ng/m3. Removable alpha 1 contamination was < 50 dpm/100 cm2.

I 4.3.3 Electrode Assembly

Gamma radiation fields were at the natural background level I throughout the area at about 5 jxR/h. At the wall beside the coating ' room the gamma field was as high as 20 (jtR/h. I The total alpha contamination was found to be less than 280 dpm/ 100 cm2 throughout the electrode assembly, electrode press and furn- ace areas. Removable alpha contamination on the floor areas outside I the coating room was 70 dpm/100 cm2- and less except on the table where electrodes were welded. There the removable alpha contamina- tion was 180 dpm/100 cm2 . Th232 concentrations in air were measured at .124 and .038 with open face filters and .036 n-g/rn3 with the cyclone separator.

4.3.4 Coating Room

Gamma radiation fields in the coating room averaged 37 (iR/h throughout the room and were a maximum of 50 (iR/h at the storage rollers for the thorium stock solutions.

In the coating room total alpha contamination levels were ineasured on the floor in the range of 280 to 840 dpm/100 cm2. On the work - 18 -

bench the levels were much higher at 55U0 to 7UUU dpin/IGG cm2. Removable alpha contamination was only bO dpm/10U cm2 on the same bench top where the total alpha was 7000 dpm/l(J!J cm2. The highest level of removable contamination was 60G0 dprn/lOG cm in the thorium storage cabinet. Of the other 7 wipes taken on floors and benches the highest was 89Q dpm/100 cm2.

During the time that subject BIO was coating electrodes the Th232 concentrations in air were measured at 3.8, 3.7, 3.0 and 1.96 (ig/m with the cyclone separator. While B3 was doing the same work Th232 concentrations in air were measured at 2.0 and 0.92 |ig/m3.

4.3.5 Coating Room Exhaust - Environmental

Gamma radiation readings were made around the exhaust fan, filter and ductwork which removes the fumehood air from the coating room. A radiation reading of 115 |iR/h at contact with the filter box indicates the presence of thorium. Along the ductwork, radiation fields of 32 nR/h were found above the duct and 80 p.R/h was found below, indicating that thorium powder was lying inside the duct itself.

Thoron daughter concentrations were measured in the exhaust air from the coating room and were calculated to be less than 1 Bq/m3.

Th232 concentrations in exhaust air were calculated to De 2.6, 1.3 and 9.4 ng/m3 even though there is an inline filter.

Roofing gravel was collected at a distance of 4 metres from the coating room exhaust stack and analysed for Th232. The thorium concentration was measured at 75, 74, 108 and 99 ppm to the north, south, east and west respectively. These levels are much higher than the 2.0 ppm that was measured in a roofing gravel sample taken from a section of roof about 50 metres from the vent.

4.3.6 Mixing Room

In the mixing room the total alpha contamination is 3600 dpm/100 cm2 in front of the storage rollers and 660 to 1400 dpm/100 cm2 in between the glove box and ball mill. The remaining floor and bench areas of the mixing room measured less than 280 dpm/100 cm2. There is very little removable contamination on the floors and benches throughout the lab; maximum is 260 dpm/100 cm2. Significant remov- able contamination was found on the plastic bottles used to store the thorium solutions, 1240 dpm/100 cm2; under the storage rollers, 9480 dpm/100 cm2; under the ball mill, 3290 dpm/100 cm2; on the ball mill, 7320 dpm/100 cm2 and in the drawer used to store thorium transfer and measuring containers.

Gamma exposure rates throughout the room average 55 except at the storage rollers, 110 (iR/h and at the glove box, 800 - 19 - I Personal air sampling with the cyclone separator was carried out while subject B7 prepared thorium dioxide solutions. On one occasion a Th232 concentration of 13.8 ng/rn3 was measured over a period of I 1.5 hours and 0.96 (ig/rn3 was measured over 7.5 hours. While non thorium work is carried on in the mixiny room the Th232 concentra- I tions in air are quite low, e.g. 0.19 and <0.09 3 Immediately to the east of the mixing room is a small office with two desks. The exposure rates at the desks are 33 and 17 nR/h I respectively and at the wall common to the mixing room it is 52 p.R/h. These fields originate from the thorium dioxide stock stored in the glove box. On the south wall of the mixing room there is an exposure I rate of 25 jiK/h from the thorium stored in the bottles on the rollers. I 4.3.7 Mixing Room Exhaust - Environmental Soil samples were taken from directly under the exhaust duct and from an area 10 metres to the north. The Th232 concentrations were I found to be 2.9 ppm (±7.1%) and 2.3 ppm (±11*) respectively. Exhaust air was sampled using open face filters and they were analysed for Th232. Dayshift Th232 concentrations in the exhaust air I were calculated to be 0.03 (±10%), 0.049 (±4%), <0.02 and <0.0079 |ig/m3. During the nightshift the concentrations were <0.005 |ig/rn3 . I 4.3.8 Contact Beta-Gamma Exposure Rates

The contact beta-gamma exposure rates were measured with TLDs on pieces of thorium metal and finished electrodes (Table 4.2-3). The results show that the exposure rates average 30 and 17.3 mR/h with 19 mg/cm2 filtration and 19 mg/cm2 filtration pïus a cotton glove respectively. At the 27 mg/cm2 filtration level the exposure rate is no different with or without the glove within the accuracy of these measurements. Although the metal is not handled very often, the wisdom of using tweezers and not relying on gloves is apparent.

The contact exposure rate from electrodes is 0.63 mR/h and less, as would be expected, because of the small amount of thorium on them.

5.0 PERSONNEL MONITORING

Bioassay measurements for thorium and it's daughter products were made on volunteers from both facilities. The measurements included in vivo determinations by whole body counting, lung counting and thoron in breath measurements. Also, 24 hour urine and fecal samples were collected and were analysed for thorium and radium- Volunteers were transported to in vivo counting facilities at the Radia- tion Protection Bureau (RPB) Health and Welfare Canada in Qttav.q and the Atomic Energy of Canada Limited Research Company (AECL-RC) Laboratories at Chalk River. Urine and fecal samples were collected at the volunteers' homes and were sent to AECL-RC for analysis. The - 20 -

subjects with detectable lurty burdens are also those subjects with Ion y work histories in areas of highest potential thorium uptake.

5.1 Methods And Calibrations

5.1.1 Whole Body Counting

Whole body burden measurements were made of subjects from Facilities A and B in the shadow shield at (AECL-RC) laboratories at Chalk River. The shadow shield is located in the Low Background Building No. 560 and the detector is a 29 cm diameter by 10 cm thick sodium iodide crystal locked in the top of the shield. A complete description of the equipment and the method is given in (Pe83).

Before the measurement, subjects were required to shower and wash their hair and they were provided with a clean set of disposable clothes. For the first part of each measurement the subject assumed a prone position on the shadow shield stretcher. The stretcher is powered by a worm gear and transports the subject under the detector at a uniform speed. For the second part of the measurement the subject assumes a supine position and is transported back to the start- ing position.

Sensitivity tests have been made using a bottle phantom and they have shown that variations in the radionuclide distribution in the phantom (in head, thorax, trunk, etc.) result in less than a 109» change in the count rate per becquerel of body burden.

The gamma ray that was used to determine body burden in this I case was the 2.6 MeV radiation from T1208. The results are quoted on the basis of Th232 activity assuming that secular equilibrium has been established, that no thoron gas escapes in either the subject or the I phantom and taking into account the 3656 branching ratio for T1208. The calibration factor used here was based on a model given in (Pe83).

5.1.2 Lung Counting

Lung/organ burden measurements were made on the subjects from I Facilities A and B at AECL-RC labs at Chalk River and at the RPB in Ottawa.

I At Chalk River, the lung burder, measurement equipment consists of two phoswich detectors, amplifiers and multichannel analyser and is located in Building No. 560. Each detector has a diameter of 12.7 cm, I 0.1 cm thick front crystal of Nal(Tl) and 5 cm thick back crystal of CsI(Tl). The female subjects were measured in a prone position with hands under the head and the phoswich detectors were positioned over the lungs above the back. The male subjects were measured in a sup- ine position with hands at the side and the phoswich detectors were positioned over the chest. A net count for each subject was calculated by subtracting a background count from the subjects gross count. The background value to be subtracted was established by measuring - 21 -

a matched subject with no lung burden. The calibration factor applied to the net counts was determined by measurement of the Lawrence Livermore Phantom (from RPB) with thorium loaded lungs. The radia- tions detected by this method are mainly the 75, 77 and 87 keV x-rays from Pb212 (Ko8l). The results are quoted on the basis of Th232 acti- vity assuming that secular equilibrium has been established and that no thoron gas escapes in either the subject or the phantom. A complete description of the equipment and the method is given in I (Jo76). Organ burdens of the subjects from both facilities A and B were I measured on one occasion at the Radiation Protection Bureau in Ottawa. Two planar hyperpure germanium detectors were used to make a total of four measurements on each subject. Alternately, the I two detector set was located 1 cm above the dorsal surface of the subject over the right lung, left lung, liver and knee. Each of the resulting gamma spectra was searched for the presence of photopeaks at 75, 77 and 87 keV which would indicate the presence of Pb212. The I net area of the combined photopeaks was determined by subtracting ! the background beneath it. This background was calculated from the subject's own spectrum by assuming a straight line between the backgrounThe detectod levelrs osysten eacmh sidwaes o f calibratethe photopeaksd for . right and left lung measurements using the Lawrence Livermore Phantom and the lung set loaded with natural thorium. Liver and knee joint calibrations were not possible because the corresponding thorium loaded organs are not yet available. For the purposes of calculating organ burdens it was assumed that all of the thoron gas was retained in both the phantom's and the subjects' lungs and that secular equilibrium had been established throughout the Th232 chain down to Pb212.

5.1.3 Thoron In Breath I The thoron in breath measurements were made on each of the subjects at AECL-RC using the following method. The subject was required to lie in a restful position for 30 minutes and breath into the I mouthpiece of the apparatus. The air was directed into a 37.7 litre | metal cylinder in which essentially all of the thoron gas decayed. The Pb2'-2 was collected on a small disc which was held at 4000 volts rela- tive to the container shell. After collection the samples were held for I 170 minutes to allow the decay of interfering radon222 daughters. The Pb212-Bi212 was then counted on a zinc sulphide scintillation detector during the 170 - 1010 minute interval after sample collection. I About 50 (uncontaminated) controls have been counted at AECL-RC and it has been concluded that 20 - 30 counts in the 170 to 1010 minute counting interval represents normal background. A count above 40 likely indicates a lung burden. The exhalation rate of thoron 1 (Rn220) in mBq per minute by the subject can be calculated by multiplying the counts in the 170 to 1010 minute interval by a factor of 0.002 mBq per minute per count. I - 22 - I 5.1.4 Urinalysis I Urine samples were collected from the subjects during weekends while they were away from the work environment. Each voidiny throughout a 3Q hour period was collected in a separate container. The samples which most closely approximated voidings from a continu- I ous 24 hour period were combined and sent for thorium, Ra224 and Ra228 analysis.

I The thorium analysis follows the gross (actinide) alpha method described in (Kr83-l). The Th232 and Th228 which were precipitated from each sample were alpha counted with a detection limit of about 0.1 mBq. The Ra224 analysis follows the calcium phosphate precipita- I tion method described in (Kr83). The separated sample is immediately alpha counted with an estimated detection limit of U.2 mBq. The Ra228 measurement is carried out on the samples prepared for Ra224 analysis I after a 90 day period has passed to allow the ingrowth of Th228 and the decay of Ra224. The alpha count of the Th228 results in a detec- tion limit of about 1 rnBq per sample. Above the detection limit the I major source of uncertainty is due to variations in the chemical recov- ery from one urine sample to another as the pH or solid fraction var- ies. The recovery is typically 75% but can vary by plus or minus 25%.

5.1.5 Fecal Analysis

Fecal samples were collected from the subjects at their homes and stools which most closely approximated 24 hour samples were combined and sent for analysis.

The samples were chemically digested and then the analytical techniques described for the urinalysis were used for the fecal samples also.

5.1.6 Hair and Nail Analysis

Samples of hair and finger and toe nails were collected from each of the subjects. The samples were measured for Th232 content by neut- ron activation analysis using the method described in Section 4.1.7. The subjects were asked to remove all nail polish and thoroughly wash the hair before donating the samples. However, the samples were not cleaned in any other way.

5.2 Facility A Results

5.2.1 Whole Body Counting

J Nine subjects from Facility A were measured in the Whole Body counter at AECL-RC in March 1984. Three subjects were taken back 3 months later in June for repeat measurements. Measurements were I not repeated on the other six subjects because their lung and body burdens were below the detection limits of the systems used and there I - 23 -

was negligible potential for significant thorium uptake in the interim. The results of the measurements are shown in Table 5.2-1. Only I subject A6 had a measurable burden and within the statistical accuracy of the measurement there was no difference between the two results.

I 5.2.2 Lung Counting

The same nine subjects from Facility A were measured in the lung I counter at AECL-RC in March 1984 and three were repeated in June. Only subject A6 had a measurable burden and within the statistical accuracy of the measurement there was no difference between the two I results. The results are shown in Figure 5.2-1. The nine subjects from Facility A were also measured at RPB in March 1984. Subject A5 was the only one identified as having a I measurable burden. However, it was concluded that it was likely due to external contamination. The burdens of the other 8 subjects were I below the detection limits of the system.

5.2.3 Thoron In Breath

I Nine subjects from Facility A were measured for thoron in breath at AECL-RC in March 1984 and three were retested in June. The results shown in Table 5.2-2 are the counts in the 170 to 1010 minute I interval after sample collection and the calculated thoron exhalation rate in mBq/minute at the mouth. Only three subjects were exhaling thoron at a rate that was considered greater than normal in March. I Repeat measurements on these three indicated that two of them, A6 and A7 had no change in thoron exhalation rate whereas, subject A9 which had been on the borderline in March was likely exhaling thoron I at the normal rate of up to 80 mBq Rn220 per minute.

5.2.4 Urinalysis

The March and August urinalysis results are given in Tables 5.2-3 and 5.2-4 and are summarized in Table 5.2-1. ICRP-23 reports that the normal rate of thorium excretion in urine is 0.1 jig/day (0.4 mBq per day). Also, ICRP-23 reports that Ra226 is normally excreted in urine at 0.08 pCi/day (3 mBq/day). The results of the March urinaly- sis tests indicated Th232 concentrations in urine significantly above that of the normal population. However, this was not supported by the results of the second set of tests in August which were much low- er. Also, there was no correlation between the two sets of results. The Ra22"4 elimination rates are similar in the normal population. The Ra228 results while large in some cases are not correlated with lung burdens nor thoron in breath results and they reflect normal excretion rates of radium. No Ra22"* and Ra228 results were obtained from the March samples because contaminated resin interfered with the measurements. - 24 -

5.2.5 Fecal Analysis

The results of the March fecal analysis are shown in Table 5.2-5. CCRF-Z3 reports that nonnally thorium is excreted in feces at 2.9 |iq/day or 12 mBq/day. Also, Ra226 is normally excreted in feces at 2.2 pCi/day or 81 mBq/day. Since the measured excretion rates are I those expected from normal subjects it was decided that the second set of fecal testing not be made. I 5.2.6 Hair And Nail Analysis I The results of the neutron activation analysis of hair and nails are given in Table 5.2-6. The thorium in finger and toe nails was not correlated with the lung burden and thoron in breath results. The Th232 in the hair of A6 suggests a relationship with thorium lung I burden however this is not supported by the result for subject A7.

I 5.3 Facility B Results

5.3.1 Whole Body Counting

I Ten subjects from Facility B were measured in the Whole Body Counter at AECL-RC in March 1984. Six subjects were retested five months later in August. Subjects B2, B3, B6 and B7 were remeasured I because the results of the March lung burden and/or thoron in breath measurements indicated possible thorium burdens. Subject B8 had just begun work in the coating room in January 1984 and it was considered prudent to retest this subject. Subject BIO had a long history of potential thorium exposure but had missed the March measurements because she had been on maternity leave. The results of both sets of whole body measurements revealed no subjects with body burdens above the detection limit (Table 5.3-1).

5.3.2 Lung Counting

Ten subjects from Facility B were measured in the Lung Counter at AECL-RC in March 1984 and six were measured in August. Only two subjects had measurable burdens; within statistical uncertainty there was no change in B3's burden and subject BIO had only been measured once (Table 5.3-1).

The ten subjects from Facility B were also measured at RPB in March in 1984. Subject B3 was reported to have 5 j-15 mg Th232 (20 + 60 Bq) in each lung. This is in some agreement with the result reported by AECL-RC. The other nine subjects (excluding BIO) were reported to have lung burdens below the detection limits of the measurement technique. - 25 -

5.3.3 Thoron In Breath

The results of the thoron in breath measurements on the subjects from Facility B are given in Table 5.3-2. The counts on each filter between 170 and 1010 minutes after the end of sample collection have been converted to thoron exhalation rates at the mouth. Between March and August subject B2 apparently dropped from 167 to 30 Bq/min at a statistically significant level. The results for three other subjects B3, B6 and B7 remained unchanged and the results for B8 increased slightly between March and August.

5.3.4 Urinalysis

The urinalysis results are reported in Tables 5.3-3 and 5.3-4 and the adjustment for excretion period has been made. The results are I summarized in Table 5.3-1 and it is apparent that the excretion rates are similar to those observed in the normal population where rates can I vary by an order of magnitude. 5.3.5 Fecal Analysis

I The fecal analysis results did not have to be adjusted since they already represented outputs for 24 hours. The results of the fecal analysis are shown in Table 5.3-5 and also are not significantly differ- I ent than the normal. Therefore, the second set of fecal analysis was cancelled for Facility B subjects also.

5.3.6 Hair and Nails Analysis

The results for the hair and nail measurements are reported in Table 5.3-6. The results are random and not correlated with lung burdens nor thoron in breath measurements.

6.0 SOLUBILITY IN SIMULATED LUNG FLUID

The solubility in simulated lung fluid, SLF, tests were carried out at AECL-RC in Chalk River and included the measurement of thorium, radium-224 and uranium.

The simulants and methods used have been described by Eidson and Griffith in the Health Physics Journal (Ei84). The composition of the simulated lung fluid is given in Table 6-1 and the method was simi- lar to the batch/filter method described by Eidson. A weighed portion of material was added to the SLF, the pH was adjusted to 7.3 and the

container was sealed with a CO2 atmosphere above the solvent. The sample was agitated in a shaker throughout the experiment and remained at room temperature. Five days out of seven the SLF was centrifuged and filtered to separate the dissolved and undissolved thorium. Fresh SLF was added to the undissolved thorium and the sample was prepared again as described above. The supernate was 1 - 26 - chemically separated and the uranium, Ra2 and thorium (gross I alpha) concentrations in SLF were measured by alpha countiny.

232 A one gram sample (3760 Bq of Th assuming pure ThO2) of thorium dioxide from Facility B was subjected to the solubility test ( described above. The concentrations of soluble thorium, uranium and Ra22M in SLF were measured on days 1, 3, 10 and 30 and the results are given in Table 6-2. I ™ Based upon a SLF batch size of 300 ml, and a starting activity of 3760 Bq thorium the amount dissolved per day in Bq/day and as a fraction of the undissolved thorium have been calculated and the ( results are shown in Table 6-3. The first day results are higher than the other three and represent a slightly greater dissolution rate which is insignificant with respect to the following analysis. * The fractional dissolution rates of thorium for days 3, 10 and 30 are not different at a statistically significant level and were used to calculate the dissolution half time of 690 years - definitely a Class Y i material.

The uranium contamination in the thorium dioxide is also class Y based upon the dissolution rates given in Table 6-2.

The Ra22VTh232 activity ratio in the Facility B thorium dioxide was measured at 0.60 ± .045 (section 4.1.9). Therefore, the undissolved Ra22Lt activity at the beginning of the study was 3760 x 0.60 = 2256 Bq (±7.5515). The dissolution rate was fitted by a function which was the sum of two exponentials; 85% of the radium had a dissol- ution constant of 9.0 x 10"5 per day (Y class) and the remaining 15* has a dissolution constant of 0.045 per day; a VV class material.

A thorium nitrate sample from Facility A was also tested for solubility in simulated lung fluid. As soon as the one gram of material was added to the 300 ml of SLF the nitrate dissolved. Almost immedi- ately it formed an insoluble complex (perhaps phosphate) with the fluid. The material although not initially a class Y material had been transformed into one. The experiment was therefore not continued.

7.0 EVALUATION OF RADIOLOGICAL SIGNIFICANCE AND RECOMMENDATIONS

During the course of the measurements at the two facilities it became apparent that some aspects of the radiological significance of the findings were distinctly different at the two plants. At Facility A the risk to non Atomic Radiation Workers was primarily due to thoron daughters in air while gamma radiation and Th232 in air were less important. On the other hand, at Facility B the inhalation of Th232 is the significant exposure pathway.

The significance of the results of the bioassay measurements at both plants were similar. In vitro measurements of radioactivity in urine, feces, hair and nails were not good indicators of lung or body burdens. I - 27 - I Lung burdens were identified in subjects from both plants by gamma I spectrometry and thoron in breath techniques. A6 was the only subject from Facility A who had a detectable lung burden by whole body or lung counting. The statistical uncertainty in each measurement is so large that none of the results can be said to be I different than any of the others. Therefore, the average burden and the observed standard deviation among the results were calculated to be 37 ± 13 Bq Th232. Subject A6 had worked with thorium at Facility A 1 from 1955 to 1983. If a chronic exposure for a period of 28 years is assumed, then the lung and lymph burden resulting from the inhalation of a Y Class material was calculated to be 130 + 96 = 226 units for one unit per day intake using Johnson's ICRP lung model tables (Jo83). I Therefore, a lung and lymph burden of 37 ± 13 Bq would result from a daily intake of 37/226 = 0.164 ± 0.051 Bq/day. Based on the Th232 I dose factor for inhalation of Y Class material (3.7 x 10"3 Sv/Bq) • (Jo83) the annual increment in the committed effective dose equivalent for each of the 28 years would have been: I 0.164 x 365 x 3.7 x 10"3 = 0.022 ± .008 Sv. There would be an additional dose from the inhalation of Th228 ( which was measured at 0.43 ± .05 relative to the activity of Th232. The annual increment in the committed effective dose equivalent from the Th228, dose factor of 1.1 x 1G"4 Sv/Bq (Jo83), would have been: I 0.164 x 0.43 x 365 x 1.1 x 10"4 = 0.0028 ± .001 Sv. Other daughters of Th232 would have been inhaled also but the doses would have been insignificant because their dose factors are I much lower than those for Th232 and Th228. In total, assuming a chronic exposure over 28 years, the increment in the committed effective dose equivalent rate to subject A6 from the inhalation of I thorium nitrate would have been 0.025 ± .0075 Sv per year.

Similar dose calculations were made for the subjects B3 and B10 using their respective lung burdens and years of exposure. The I annual increments in the committed effective dose equivalent rates were calculated to be 0.017 ± 0.011 Sv per year for 11 years and 0.025 ± .018 Sv/y for 7 years respectively. The doses to subjects A6, B3 I and B10 represent 50*, 34* and 30% respectively of the limit of 0.05 Sv/y for Atomic Radiation Workers. With appropriate modifications to equipment and practices as described below, future doses can be I reduced to much lower levels. The results of the thoron in breath measurements on all three subjects who had lung burdens detected by lung and whole body I counting were above the level for normal uncontaminated subjects. In addition, the thoron in breath technique identified two other subjects, A7 and B6, who likely had lung burdens below the detection limits of I the other methods. The calculation of lung burden using thoron in breath results is very sensitive to the rate at which thoron gas escapes from the thorium particles in the lung and into the mouth. It I is therefore necessary to determine the actual particle size distribution I - 28 -

of the thorium in the lung. The rates at which thoron escapes from the mouths of subjects A6, B3 and BIO have been calculated relative to the measured lung burden as 1.0 t ,b%, 1.7 t 1.8% and 2.8 ± 2.3^b respectively. Thoron in breath measurements are the most sensitive indicator of lung burdens but cannot be used to calculate lung i burdens with presently known data. The fractions of the annual effective dose limit (5 mSv/y) received by non Atomic Radiation Workers occupying each room in Facility A for 1 2000 hours per year have been calculated and are shown in Figure 7-1. The calculations have been based upon the inequality given on page 54 of 1CRP 30 Part 1 and the following limits were used: 0.88 ng/m3 Th232 and daughters; 33 Bq/m3 thoron daughters (1CRP 32) and 2.5 I |iSv/h gamma radiation. In the four rooms with the largest fraction of the dose limit, thoron daughter concentration in air was the predomin- ant contributor in each case.

Environmental pathway analyses were made using existing metabol- ic and dosimetric models to determine the maximum acceptable concentration of Th232 in soil that could be allowed to safely pass out of control of the licencee. Calculations were made for all pathways indicated in Figure 7-2 and the critical pathway was found to be the soil-vegetation-man pathway with Ihe critical group, adults. It was assumed that the land was being used by a group of adults who consumed fruits and vegetables grown on the thorium laden soil. For the purposes of these calculations, it was assumed that each adult consumed 255 kg per year (Ss57) of fruit and vegetables. Transfer factors for Th232 and daughters from soil to vegetation were taken from reference Ss57 and the corresponding dose factors were taken from Jo83, see Table 7-1.

It was calculated that under the above circumstances a thorium in soil concentration of 0.25 Bq Th232/g soil, (62 \iq Th232/g soil), would result in a committed effective dose equivalent rate of 5 mSv per year to each member of the critical group. Therefore, 62 ng/g should be considered the upper limit for soil to be released from the licencee's control into the public domain.

Thorium processing was discontinued at Facility A, however, in the future workers will carry on other tasks in the areas indicated in Figure 7-1. In some areas remedial action is necessary to ensure that no member of the general public receive a radiation dose exceeding 5 mSv in any given year. Also, some simple cleanup operations have been identified which will reduce actual or potential doses in keeping with the ALARA principle, "as low as reasonably achievable, taking into consideration other economic and sociological factors."

The walls and floor near the mixing area in the pre-1970 thorium room should be decontaminated and the walls and floors sealed (with paint and varathane for example). When the property is sold or renovated these sections of wall and floor should be disposed of in an approved dump site.

No action is required in the east room, south room, lunch room and adjacent manufacturing areas on the second floor. - 29 -

The machine room, thorium room and mantle manufacturing area on the second floor require remedial action in two stages. At the next convenient shutdown these areas should be decontaminated and the wooden benches disposed of to an approved dump site. The walls and floors should be sealed with paint and varathane to reduce the escape of thoron gas into the room air. In the longer term when major I renovations are next carried out or the property is sold, the thorium impregnated walls and floors should be taken up and disposed of to an I approved dump site. The ladies change room should have continuous ventilation to reduce the thoron daughter concentration in air. The exhaust fans I were shut down during the time when all the air sampling was carried out.

The inner courtyard requires no remedial action at this time. I However, when renovations are carried out or upon the sale of the property, the waste material should be removed and transported to an I approved dump site. The test lab requires only cleanup of the removable contamination I that remains on the drop test equipment and the burn test bench. The storage room requires no action as no traces of the previous uses remain.

I The following changes are recommended at Facility B. In the mix- ing room:

- The glove box should be increased in size so that all of the equipment for thorium preparation can be kept inside it. This will eliminate the potential for the spread of thorium contamination when the equipment is put into storage in the drawers.

- The procedure for preparing the thorium mixture should be modified to allow the addition of liquid to the thorium powder in the glove box. Then the transfer to the ball mill will involve a wet trans- fer rather than the current dry transfer. There would be a reduction in the thorium particulate in air concentrations to which the workers would be exposed.

- All thorium laden waste including wet rags and liquids should be disposed of into the radwaste collection system. This may require the use of liquid absorbent such as selite but would likely be cheaper than installing a holding tank and analysing the liquid before dumping it into the sewer.

- Gloves that are worn during sample preparations and become contaminated should not be put into the glove box gloves.

In the coating room a number of changes are recommended with reference to equipment and procedures for reducing thorium inhala- tion. - 30 -

- Operator habits regarding smoking should be improved. The smoking ban in the coating room should be maintained and a special effort should be made to impress upon the workers that improved hygiene habits can significantly reduce thorium uptakes. Specifically, cigarettes should not be handled with gloves (or hands) contaminated I with thorium powder. - A glove box should be installed in which all stages of the coating operations can be carried out. It should be large enough to include ( thpe ultrasnniultrasonicn hathbath., the evacuatiopvar-tiaHnn chambenhwmhpr and a small garbagnarhanep container. I - Waste removal from the glove box should take place as follows; the plastic bag containing waste in the glove box should be closed and tied. At removal from the glove box it should be put into a clean bag I and again tied. The exhaust system for the coating room and the procedures I associated with it should be modified as follows; - When filter changes are made, a plastic bag should be positioned so that the filter can be transferred directly into it to minimize the spillage of dust. Any dust that is spilled should be cleaned up. A vacuum cleaner with an absolute filter is appropriate for this task.

- The thorium powder is very fine and an absolute filter should be used in the exhaust duct. To extend the lifetime of the absolute filter it is prudent to install a prefilter to catch dust and large particulates.

- The horizontal section of the exhaust piping is loaded with thor- ium dust and should be cleaned out. When this cleaning is carried out it would be advisable for the workers to wear dust masks and wet the thorium powder where possible.

- Workers in the mixing and coating room under present condi- tions must be classified as Atomic Radiation Workers. If the annual effective dose equivalent for these workers cannot be reduced below 309» of the limit, individual personal air sampling should be instituted as per the recommendations regarding Working Condition 'A' in Basic Requirements for Personnel Monitoring (Ssl4). However, it is highly likely that the installation of and proper use of a glove box will reduce the dose rate and eliminate the need for personal monitoring. Semiannual lung burden and thoron in breath measurements should be established as routine until intakes have been shown to be effectively reduced.

8.0 CONCLUSIONS

Solubility in simulated lung fluid measurements on samples of the thorium dioxide and thorium nitrate proved that they both must be placed in the Y Inhalation Category of the ICRP lung model. It was therefore consistent that urinalysis and fecal analysis segments of the study were shown as not early indicators of significant lung uptakes of - 31 - I One of the /most .sensitive methods of detecting uptakes I appears to be thoron in breath monitoring. Unfortunately in this study too few subjects had burdens measureabie by other means for cross correlation. Information regarding the particle size is necessary to improve the accuracy of assigning lung burdens on the basis of i thoron in breath. It is recommended that a sample of the thorium dioxide be analysed for particle size distribution, however, it is not recommended that thorium nitrate be analysed this way because of the physical change it undergoes in the lung. The results of the monitoring at both facilities were consistent with bioassy measurements. The work environments that were identi- fied as high potential for thorium inhalation were the v\ork areas of the i subjects with rneasureable lung burdens. There was a distinct differ- ence between the potential risks at the two facilities. At the facility that used thorium dioxide there was no risk from thoron daughters in I air because of the small inventory and tight binding of the thoron gas in the thorium dioxide particle. The material was very fine and does present a high potential for inhalation. The addition of a glove box at Î the coating stage and a change to wet instead of dry transfers to the ball mill will reduce the uptakes significantly. Education for and improvements in operator hygiene specifically regarding smoking and J hand contamination should further reduce uptakes. I 9.0 REFERENCES Ba72 The Measurement of Thoron in the Breath of Dogs Administered I Inhaled or Injected ThO2; Ballou, J.E. and Hursch J.B., Health Physics, Vol. 22, 1972. Be73 Estimates of Microcurie-days Residence, Bone Dose Equivalent and (MPC)w for Thorium232 in Man Using a Mammillary Model; Bernard, 5.R., Bulletin of Mathmatical Biology, Vol. 35, 1973.

Ce76 Introduction to Health Physics; Cember, H., Pergamon Press, 1976.

Ha84 Personal Communication, Harvey, J.A., McMaster University, Hamilton, Ontario.

Ho77 Relative Filter Efficiencies for Sampling Radon Daughters in Air; Holmgren, R.M., Wagner, W.W., Lloyd and R.D. Pendle- ton, R.C.; Health Physics, Vol. 32, 1977.

ICRP23 Report of the Task Group on Reference Man; International I Commission on Radiological Protection Report No. 23, pergamon Press, 1974.

I ICRP24 Radiation Protection in Uranium and Other Mines; International Commission on Radiological Protection Report No. 24, Pergamon Press, 1977. I I - 32 - I ICKP26 Recommendations of the [nternatioru.il Commission on Radiological I Protection Report No. 26, Pergamon Près;;, 197V. ICKP29 Radionuclide Release into the Environment: Assessment of Doses to Man; International Commission on Radiological Protection I Report No. 29, Pergamon Press, L978. ICRP30 Limits for Intakes of Radionuclides by Workers; International Commission on Radiological Protection Report No. 3U, Part 1, Pergamon Press, 1970.

ICRP3U Limits for Intakes of Radionuclides by Workers; International -s Commission on Radiological Protection Report No. 3(J, Supple- ment to Part 1, Pergamon Press, 1970.

ICRP31 Biological Effects of Inhaled Radionuclides; Assessment of Doses to Man; International Commission on Radiological Protec- tion Report No. 31, Pergamon Press, 1979.

ICRP32 Limits for Inhalation of Radon Daughters by Workers; Inter- national Commission on Radiological Protection Report. No. 32, Pergamon Press, 1981.

Jo76 Measurement of Transuranic Elements In-Vivo at CRNL; John- son, J.R., AECL-5621, November 1976, Atomic Energy Canada Limited, Chalk River.

Jo80 Annual Limits on Intake, Organ Burdens and Excretion Rates for Occupationally Exposure to Uranium; Johnson, J.R., AECL-6478, March 1980, Atomic Energy Canada Limited, Chalk I River.

Jo83 Dose Conversion Factors for Intakes of Selected Radionuclides I by Infants and Adults; AECL-7919, Johnson, J.R. and Dun- ford, D.W., Atomic Energy Canada Limited, Chalk River, I January 1983. Jo84 A Model to Describe Thoron Exhalation Following an Inhalation Exposure to Thoria Aerosols; Johnson, J.R. and Peterman, B.F., March 1984 presented at Workshop on Lung Modelling I for Inhalation of Radioactive Materials, Oxford, U.K.

Jo84-1 Personal Communication, Johnson, J.R., Atomic Energy Canada I Limited, Chalk River.

Ko81 Radioactive Decay Data Tables; Kocker, D.C., DOE/T1C-11026, I Technical Information Center, U.S. Department of Energy. Kr83 The Determination of Ra226 in Urine; Kramer, G.H. and ( Beaulieu, P.C., AECL-7608, Atomic Energy Canada Limited, Chalk River, 1983. - 33 -

Kr83-1 Screening Procedures for Alpha, Beta and Gamma Lmittiny Radionuclides in Urine; Kramer, G.H., Gardner, S.E. and Johnson, J.R., AECL-7608, Atomic Energy Canada Limited, Chalk River, 1983.

Pe8 3 Whole Body Monitoring at CRNL; Peterrnan, B.F., CRNL-2582, September 1983, unpublished report available from Atomic Energy Canada Limited, Chalk River.

Ru78 The Radioactive Properties and Biological Behaviour of Ra224 (Th X) and its Daughters; Rundo, J., Health Physics, Vol. 35, 1978.

Ru79 Radioactivity in Former Workers at a Thorium Refinery; Rundo, J., Brewster, D.R., Essling, M.A. and Sha, J.Y.

St84 Personal Communication, Staniuk, S., McMaster University, Hamilton, Ontario.

Ss43 Manual on Radiological Safety in Uranium and Thorium Mines and Mills; Safety Series No. 43, International Atomic Energy Agency, 1976.

Ss49 Radiological Surveillance of Airborne Contaminants in the Working Environment; Safety Series No. 49, International Atomic Energy Agency, 1979.

Ss57 Generic Models and Parameters for Assessing the Environmen- tal Transfer of Radionuclides from Routine Releases; Safety Series No. 57, International Atomic Energy Agency, 1982.

Trl42 Inhalation Risks from Radioactive Contaminants; Technical Report Series No. 142, International Atomic Energy Agency, 1973.

Trl79 Particle Size Analysis in Estimating the Significance of Air- borne Contamination; Technical Report Series No. 179, Inter- national Atomic Energy Agency, 1978.

Ssl4 Basic Requirements for Personnel Monitoring; International Atomic Energy Agency, Safety Series No. 14, 1980. FIGURE A. 1-1

Calibration Curve of Sodium Iodide Detector Using Ra226

2 3 i S t> 7 i 9 I 1 3 i S t> T I 9

"i Counts per 30 % Seconds

10

10"

10 10 100 1000

Exposure Rate Figure 4.1-2

Calibration Curye for Sodium Iodide Detector (Ra226)

Counts g per 30 aconds

200,000

'100,000

50 100 150 200 250

Exposure Rate in wR/h mm. sum mm oïsfi :>«K

FIGURE 4.1-3

Schematic of Panasonic UD801 Thermoluminescent Dosimeter

holder Element Plate

-\3*polyamide L J 150 teflon 800 lead 800 lead

22 teflon L J 22 teflon L 22 teflonL 22 teflon

U Li B O CaSO, 'A°7 2 4 ? !1 CaSO,4 11 4

111 polyamid^" ~|11 polyamide J" |I 1 polyamide 11 polyamide

"|3 polyamide [" 150 teflon 800 lead 800 lead

Element Number

* Units are mg/cm2 FIGURE A. 1-4

EPIDERMAL THICKNESS OF FINGERS AND TLD FILTRATION

TLD Filtration

i I

Fingertips

I Fingers I

10 20 30 40 50

Epidermal Thickness/TLD Filtration mg/cm2

* + one standard deviation, taken from [ICRP23]

i FIGURE a. 1-5

ANEMOMETER CALIBRATION - HIGH RANGE FIGURE A. 1-6

ANEMOMETER CALIBRATION - LOW RANGE

600 I I

500

Feet Per 400' Minute (true)

300

200-

100.

100 200 300 400 500 600

Feet Per Minute (Indicated) FIGURE 4.1-7

Th 228/Th 232 ACTIVITY RATIO AS A FUNCTION OF TIME

SINCE SEPARATION

0.9

0.8

0.7

Th 228 Th 232 0.6 Activity Ratio

0.5

0.4 -

0.3

0.2 10 15 20 25 30 35

Time Since Separation (years) i

I FIGURE h.1-8

RELATIVE ACTIVITIES OF DAUGHTERS IN THORIUM DIOXIDE

STOCK MATERIAL FROM FACILITY B

400 I Relative Count 300 Rate 'I 200

Th232 Ra224 Po216 Th228 Rn220 Po212

Radioactive Daughters

9 ± 2 standard deviations (counting statistics)

* divided by branching ratio of Po212 so actually represents Bi212 activity FIGURE 4.2-1

GENERAL LAYOUT OF FACILITY A

City Street

• Testing Lab Railway Right of Way

./Inner Courtyard Pre 1970 Thorium Room Lunch room Storage Room .Thorium Room FIGURE 4.2-2

LAYOUT IN VICINITY OF THORIUM ROOM - FACILITY A

Lunch Room

Mantle SECOND FLOOR ÎManufacturir g

Adjacent Manufacturing -M-

Thorium

lange Room

FIRST FLOOR FIGURE A.2-3 i INNER COURTYARD COMPLETELY SURROUNDED BY BUILDINGS N FACILITY A i 4.4 I *3.4 Gamma Exposure Rate, UR/h at an elevation of 1 SCALE one metre above the Soil Under H H- ground/asphalt Asphalt (+10% - 30%) • . ^3.8 155 ppm 1 metre I Th 232

*5.9

ASPHALT •

Soil 43 ppm "13. Th 232 \

* // /* *7.9_ / 6.9/ /7.1 A 6.7 s.9 7.1 6.4 '7.9

; -*r / 4.2 5.9 BARE SOIL '

/ *• 5.9 Sewer: Soil .6.1 2330 ppm •4.3" Th 232 THORIUM STORAGE ROOM 1-5 FIGURE 4.2-4

TEST LABORATORY FACILITY A: OCCUPATIONAL ENVIRONMENT MONITORING

Mantle-Burn Bench Test Bench *7.7 7.5 4 9* / * GarbagaT^ Entrance Can V_M2 / 10*

8.2*

6.1* Bench

*6._0

Bench

Mantle Drop 5.3* Test ' Machine _ i 1 Large Door

Index - underlined numbers are exposure rates in yR/h at * - circled numbers indicated locations where wipes were taken - removable alpha, dpm/100 cm2 CD <10 dpm/100 cm2 (2) 10 ± 10 dpm/100 cm2 (5) 3370 ± 180 dpm/100 cm2 © 1040 ± 100 dpm/100 cm2 (5) 490 + 70 dpm/100 cm2

Thoron daughters is air: 1.7 ± 0.51 Bq/m3 0.8 + 0.22 Bq/m3 FIGURE 4.2-5

STORAGE ROOM FACILITY A: OCCUPATIONAL ENVIRONMENT MONITORING N

\

5.9* *5.0

STORAGE

6.6* ROOM *6.5

WALKWAY

6.0*

Sliding Door

*5.0 HALLWAY

- underlined numbers are exposure rates in yR/h at *

- Thoron daughters in air inside the Storage Room 0.4 ± 0.2 Bq/m3 FIGURE 7-1

FRACTION OF ANNUAL DOSE LIMIT (5 mSv/y) FOR NON ATOMIC RADIATION WORKERS (assuming 2000 h/year occupancy)

0.0 0.5 1.0 1.5

Test Lab

Storage Room

Pre 1970 Thorium Room

Storage

Machine Shop

South Room

East Room

Lunch Rm & Adjacent Manu.

Ladies Change Room

Thorium Room

Mantle Manufacturing

maximum measured value minimum measured value FIGURE 7-2

TH232 PATHWAYS FROM SOIL TO NAN I

I TABLE 2-1

I JOB DESCRIPTIONS AND WORK HISTORIES OF FACILITY A SUBJECTS

I Subject Number Job Description* and Work History Al 1950 to 1983

I A2 1973 to 1983 I A3 1973 to 1983 A4 1967 to 1983 I A5 1969 to 1983 A6 1955 to 1983

I A7 1966 to 1983

A8 maintenance on equipment 1979 to 1983

A9 1964 to 1983

* All subjects (except A8) rotated through all the tasks except for mixing of the solutions and dipping of the mantle materials. I TABLE 2-2 I JOB DESCRIPTIONS AND WORK HISTORIES OF FACILITY B SUBJECTS I Subject // Job Description and Work History Bl August 2, 1972 to present, 8 years on quartz lathe 1 year odd jobs, on thorium press to present

I B2 September 1983 to present, electrolytic cleaning and cutting of thorium metal and inspects electrodes I for thorium deposition B3 May 15, 1972 to present, coating room for 11 years to December 1983, since then occasionally fills in I at coating room B4 October 30, 1972 to present, on thorium presses for 9 years, for 2 years occasional work on thorium presses

B5 September 1968 to present, welding coils to hairpins

B6 November 6, 1972 to November 11, 1974 and May 18, 1981 to present, odd jobs and cleaning out radwaste from coating room

B7 April 11, 1966 to present, only person to work with thorium in mixing room

B8 December 1983 to present, works in coating room

B9 February 5, 1979 to present, mechanic maintains equipment in all thorium areas except the mixing room

BIO Started in coating room August 1975, maternity leave January - October 1980 and May 1983 to May 1984

Bll April 19, 1972 to present, all tasks except mixing room on a replacement basis TABLE 2-3

THORIUM DIOXIDE USAGE AT FACILITY B SINCE 1966

Year Batches

1967 1 1968 11 1969 15

1970 18 1971 22 each batch contained 1972 36 989 g of ThO2 1973 53

1974 14 1975 7 each batch 1976 7 contained 1978 g of ThO 1977 7 1978 9 1979 8

1980 5 1981 5 1982 3 1983 3.5 TABLE 3-1

THORIUM 232 DECAY CHAIN

Major radiation energies (MeV) Historical Nuclide Half-life and Intensitlest name or B Y

10 9 ÎTh Thorium 1.41X10 y 3.95 (24%) - --- 4.01 (767.)

33 Mesothorlum I 6.7y ... 0.055 (100%) --- a

33 8 !Ac Mesothorium II 6.l3h ... 1.18 (35%) 0.34c* (15%) 1.75 (12%) 0.908 (257.) 2.09 (12%) 0.96c (20%)

aa >Th Radlothorium l.9l0y 5.34 (28%) --- 0.084 (1.67.) 9 5.43 (71%) 0.214 (0.37.)

33 R. Thorium X 3.64d 5.45 (6%) --- 0.241 (3.7%) 8i 5.68 (94Î) I Emanation 55a 6.29 (1001) 0.55 (0.07%) 88 Rn --- Thoron (Tn)

Thorium A 0.15s 6.78 (100%) ------

I Thorium B 10.64h --- 0.346 (81%) 0.239 (477.) 0.586 (14%) 0.300 (3.2%) T• Thorium C 60.6m 6.05 (25%) 1.55 (5%) 0.040 (2%) 6.09 (10%) 2.26 (557.) 0.727 64.0% 1 36.07. 1.620 (.m (1.8%) 31 ;PO Thorium C 304ns 8.78 (100%) ... • ---

8 Tl Thorium C" 3.10m --- 1.28 (25%) 0.511 (23%) 1.52 (21%) 0.583 (86%) 1.80 (50%) 0.860 (12%) 2.614 (100%) J Thorlun D Stable

Oit« taken froa: L*derer. C. H., Hollander, J. H., and Peclun, !.. Table ot laotope» (tth éd.; New York: John U)]ey k Sons, Inc., 1967) and Hog.n, O. H., Zlgun, r. t., and Hackln, J. L., Beta Spectra (USNRDL-TH-SO2 [lfi»hln(ton, D.C.: U.S. Atoalc Energy Cooatislon, 1964]). TABLE 4.2-1

THORIUM ROOM EXHAUST STACKS - FACILITY A

Maximum Duty Cycle Average Exhaust Dimensions Air Speed Exhaust Shift Week * Ra :e Exhaust Vent in x in FPM Rate m'/s h/8h h/168h xl03m3 /8h xl03m3/168h*

Dryer Exhaust 16 x 12 1600 1.01 8 40 29 145

Lacquer Exhaust 16 x 12 2200 1.38 7 35 35 175

Ammonia Exhaust 7.75 dia 800 0.124 4 + 2 20 + 10 1.79 9.0

Old Thorium Room 12 x 9 570 0.20 0-8 0-40 0 - 5.8 0-29

New Thorium Room 13.5 x 9 1350 0.54 0-8 0-40 0 - 15.6 0-78

TOTALS 66 - 87 330 - 436

* Assuming One Shift Per Day Each of 5 Days Per Week i i TABLE 4.2-2

CONTACT BETA-GAMMA EXPOSURE RATE ON LANTERN MANTLES

I TLD Total Exposure Rate Average No. Filtration mR/h mR/h m mg/cm2

MANTLE 'X' 98 1^9 5.^.<-2 >. , I 19 4.5 96 _2.7 4...1 27 4.3

I 93 19 ") 3.5 92 19 ^• CottoCottonn 4.22 Î 3.9 I 91 19 J Glove 4.1 90 27) 3.8 89 27 >1 Cotton 3.11 f 3.5 I 27 J Glove 3.4

MANTLE'Y' I 86 19 5.0 85 19 4.1 I 83 27 3.6 82 27 3.9 I 81 19 I 4 ? 7 Cotton T 7 f 4-0 I 80 19 J Glove ' J 78 27 )? + 3.6 27 Cotton 3.3 f 3.5 I " ( Glove 3.6 I 72 27 J I I I I I I TABLE 4.2-3

CONTACT BETA-GAMMA EXPOSURE RATE ON THORIUM METAL S. ELECTRODES

TLD Total Exposure Rate Average No. Filtration mR/h mR/h i mg/cm2 THORIUM METAL « 19 31 19 30

D 7 1i 9^ Cottou w L. ^ k^in 1 16.j.vj.\6y » . _. ^ 19 Glove 18.1

67 .2,7 .^.18.5. v l85 27 18.5 27 17.4 Cotton is.6 27 19.8 Glove

ELECTRODES (one small & one large electrode on each chip) 62 19 0.57 I 61 19 0.70 5 °-63 59 [I Cotton ' °"^ I" 0.45 Glove

57 27 0.10 t 56 27 0.59 ' °-34 55 27 + 0 25 54 27 Cotton 0'2^ I 0.23 Glove TABLE 5.2-1

SUMMARY OF BIOASSY RESULTS OF FACILITY A SUBJECTS

Whole Body Lur'g Thoron iiI Breath Urin anlysis - output mBq /24 h Bq Th23 I (T1208) Bq Th232 (Pb212) mBq Rn2 20/min Gross al )ha (Th) Ra 224 Ra228 Subject March June March June March June March August March August March August

Al ND — ND — 64 i 32 — <0.19 0.08 -(1) 1.12 -(1) 4.3

A2 ND -- ND — 62 i 32 — 6.9 0.147 — 0.66 — 5.7

A3 ND — ND — 52 t 28 — 0.19 0.21 — 0.67 — 1.2

A4 ND — ND — 62 ± 32 — 0.48 0.174 — 1.07 — 11.0

A5 ND — ND — 28 i 20 — 0.80 0.35 — 2.7 — 49.0

A6 14 ± 14 68 + 133 31 ± 22 36 ± 26 271 t 86 300 ± 96 9.0 1.3 — 4.2 - <1.0

A7 ND ND ND ND 109 t 46 135 t 52 2.6 0.44 — 0.39 — 10.8

A8 ND — ND — 58 ± 30 ~ , 0.54 0.84 — 1.17 -- 39.0

A9 ND ND ND ND 82 ± 38 48 t 28 2.7 0.10 — 1.20 - cj.0

(4) (2) (3) (3)

NOTES: (1) contaminated resin (2) normal urinary excretion rate of thorium is 0.4 mBq/day [ICRP23) (3) normal urinary excretion rate of Ra226 is 3.0 mBq/day [ICRP23J (4) 80 raBq/min is considered upper limit of normal exhalation rate TABLE 5.2-2

THORON IN BREATH RESULTS - FACILITY A

Subject Net Counts Thoron in Breath 170 - 1010 min raBqRn220/min March June March June

Al 32 ± 16 — 64 ± 32 —

A2 31 ± 16 — 62 ± 32

A3 26 ± 14 — 52 ± 28 —

A4 31 ± 16 — 62 ± 32 —

A5 14 ± 10 — 28 ± 20 —

A6 136 ± 43 153 ± 48 271 ± 36 300 ± 96

A7 55 ± 23 68 ± 26 109 ± 46 135 ± 52

A8 29 ± 15 — 58 ± 30 ~

A9 41 ± 19 24 ± 14 82 ± 38 48 ± 28 TABLE 5.2-3

March Urinalysis Results - Facility A

Urine Collection Gross Alpha Activity in Urine I Subj ect Period (hours) mBq/sample mBq/24 hours Al 25 < 0. 19 < 0.19

A2 18 5.2 6.9

A3 32 0.25 0.19

A4 30 0.60 0.48

A5 24 0.80 0.80

A6 15 5.6 9.0

A7 18.5 2.0 2.6

A8 25.5 0.57 0.54

A9 21 2.4 2.7

Note: No radium results due to contamination

Alpha corrected to pure Th232/Th228, a spectrum shows very small Th 23?T0 contributionr-nnf-T-i hnfinn . TABLE 5.2-4

AUGUST URINALYSIS RESULTS - FACILITY A

Radioactivity in Urine Urine Collection mBq/sample mBq/24 hours Subject Period (hours) a Ra224 Ra228 a Ra224 Ra228

Al 24 0.08 1.12 4.3 0.08 1.12 4.3

A2 24.5 0.15 0.67 5.8 0.147 0.66 5.7

A3 25 0.22 0.70 1.3 0.21 0.67 1.2

A4 23.5 0.17 1.05 10.9 0.174 1.07 11.0

A5 24 0.35 2.7 48.9 0.35 2.7 49.0

A6 24 1.3 4.2 0.0 1.3 4.2 <1.0

A7 23 0.42 0.37 10.4 0.44 0.39 10.8

A8 23 0.08 1.12 37.4 0.84 1.17 39.0

A9 24 0.10 1.20 0.0 0.10 1.20 <1.0 TABLE 5.2-5

MARCH FECES RESULTS - FACILITY A

Feces Collection Radioactivity in Feces Subj ect period (hours) mBq/sample mBq/24 hours a Ra (e) Ra228 a Ra (e) Ra228 Al 24 29.2 4.5 9.3 29.2 4.5 9.3

A2 24 15.5 13.2 0.0 15.5 13.2 <7.0

A3 24 27.0 13.3 25.0 27.0 13.3 25.0

A4 24 13.7 20.,7 7.1 13.7 20.7 7.1

A5 24 27.3 69..5 0.0 27.3 69.5 <7.0

A6 24 10.8 41..5 160.0 10.8 41.2 160.0

A7 16 28.3 40..5 0.0 42.5 61.0 <7.0

A8 15 33.5 33.,8 0.0 54.0 54.0 <7.0

A9 24 46.3 15.7 85.0 46.3 15.7 85.0

(e) mainly radium 226

I \ I I TABLE 5.2-6

Th 232 IN HAIR AND NAILS - SUBJECTS FROM FACILITY A

Subject Th 232 Content in Parts per Million Toe & Finger Nails Hair

Al 11 .9 (±5% ) 0. 3 (±36%)

A3 3 .9 (±13%) < 0. 3

A5 < 0 .8 < 0. 24

A6 4 .8 (±9.6%) 13. 8 (±4.1%)

A7 9 .5 (±8.3%) 0. 3 (±37%)

A9 2 .0 (±11%) < 0. 19 TABLE 5.3-1

SUMMARY OF BIOASSY RESULTS OF FACILITY B SUBJECTS

Whole Sody' -ung Thoron i n Breath Urinalys i s - 3u t pu t mBe /24 hours Bq Th232 (T1208) Bq Th2)2 (Pb212) mBq Rn220/min Gross aIpha (Th) Ra22 R,i228 Subject March August: March August March August March August March Augus t March Augi st

Bl ND ~ ND -- 68 ± 34 — 0.0 0.0 0.0 1.22 <1.0 <\. 0

B2 ND ND ND ND 167 ± 62 30 ± 12 0.0 0.13 0.0 2.3 0.89 <1.0

B3 ND ND 22 ± 22 20 i 24 240 ± 80 290 ± 92 0.044 0.0 0.0 2.0 0.39 <1.0

B4 ND " ND -- 36 ± 22 ... 0.077 0.13 1.23 0.40 <1.0 3.3

B5 ND — ND — 76 ± 36 — 0.0 0.35 1.6 1.7 0.89 <1.0

B6 ND ND ND ND 82 ± 38 113 ± 32 0.26 0.20 0.0 1.8 <1.0 14.3

B7 ND ND ND ND 125 ± 50 117 ± 34 0.0 0.10 4.6 4.2 28.0 <1 0

B8 ND ND ND ND 30 ± 20 74 ± 22 0.0 0.13 0.10 1.5 0.61 1 2

B9 ND — ND — 40 ± 24 — 0.30 0.18 0.0 0.36 3.0 18 0

BIO — ND — 29 ± 24 — 610 ± 125 — 0.067 — 25.0 — <1 0

Bll ND — ND — 34 ± 22 — 0.0 0.017 1.78 0.73 73.0 16 3

(3) (1) (2) (2) NOTES: (1) normal urinary excretion rate of thorium is 0.4 mBq/day [ICRP23] (2) normal urinary excretion rate of Ra226 is 3.0 mBq/day [ICRP23] (3) 80 mBq/min is considered upper limit of normal exhalation rate TABLE 5.3-2

THORON IN BREATH - FACILITY B

Subject Net Counts Thoron in Breath 170 - 1010 min mBq Rn220/min March August March August

Bl 34 ± 17 — 68 ± 34 —

B2 84 ± 31 15 ± 6 167 ± 62 30 ± 12

B3 122 ± 40 144 + 46 240 ± 80 290 ± 92

B4 18 ± 11 — 36 ± 22 —

B5 38 ± 18 — 76 ± 36 —

B6 41 ± 19 57 ± 16 82 ± 38 113 ± 32

B7 63 ± 25 59 ± 17 125 + 50 117 ± 34

B8 15 ± 10 37 ± 11 30 ± 20 74 ± 22

B9 20 ± 12 — 40 ± 24 ~

B10 — 305 + 63 — 610 + 125

Bll 17 ± 11 — 34 ± 22 — TABLE 5.3-3

MARCH URINALYSIS RESULTS - FACILITY B

Radioactivity in Urine Urine Collection mBq/saraple mBq/24 hours Subject Period (hours) a Ra224 Ra228 a Ra224 Ra228

Bl 22 0.0 0.0 0.0 0.0 0.0 <1.0

B2 29 0.0 0.0 1 07 0.0 0.0 0.89

B3 27.5 0.05 0.0 0 45 0.044 0.0 0.39

B4 25 0.08 1.28 0 0 0.077 1.23 <1.0

B5 19.5 0.0 1.3 0 72 0.0 1.6 0.89

B6 25 0.27 0.0 0 0 0.26 0.0 <1.0

B7 17.3 0.0 3.3 20.0 0.0 4.6 28.0

B8 24.5 0.0 0.1 0.62 0.0 0.1 0.61

B9 12 0.15 0.0 1.5 0 3 0.0 3.0

Bll 23 0.0 1.7 70.3 0 0 1.78 73.0 TABLE 5.3-4

AUGUST URINALYSIS RESULTS - FACILITY B

Radioactivity in Urine Urine Collection mBq/sample mBq/24 hours Subject Period (hours) a Ra 224 Ra228 a Ra224 Ra228

Bl 25.5 0.0 1.3 0.0 0.0 1.22 <1.0

B2 24 0.13 2.3 0.0 0.13 2.3 <1.0

B3 24 0.0 2.0 0.0 0.0 2.0 <1.0

B4 23.25 0.13 0.40 3.4 0.13 0.40 3.3

B5 24 0.35 1.7 0.0 0.35 1 .7 <1.0

B6 24 0.20 1.8 14.3 0.20 1.8 14.3

B7 23 0.10 4.0 0.0 0.10 4.2 <1.0

B8 27 0.15 1.7 1.4 0.133 1.5 1.2

B9 20 0.15 0.30 15.2 0.18 0.36 18.0

BIO 24 0.067 25.0 0.0 0.067 25.0 <1.0

Bll 23.5 0.017 0.73 0.62 0.017 0.73 0.63 TABLE 5.3-5

MARCH FECES RESULTS - FACILITY B

3 Subj ect inBq Excreted er 24 Hours a Ra224 Ra228

Bl 9.8 < 1 30.

B2 27 .0 35 < 8.

B3 13.0 1.2 92.5

B4 4.0 < 1 14.3

B5 35 • 1.3 < 8.

B6 31 42. < 8.

B7 6 .3 30. 7.7

B8 31 42. < 8.

B9 17 23. < 8.

Bll 6 8 28. < 8. TABLE 5.3-6

TH232 EN HAIR AND NAILS - SUBJECTS FROM FACILITY B

Subject Th 232 Content in Pi rts Per Million Toe & Finger Nails Hair

B2 1.0 (±22%) < 0.17

B3 < 0.4 < 0.12

B5 4.6 (±9.6%) 1.28 (±9%)

B6 2.8 (±7.2%) < 0.13

B7 0.4 (±45%) < 0.5

BIO 11.7 (±8.7%) 0.56 (±13%)

Bll < 0.4 < 0.15

I TABLE 6-1

COMPOSITION OF SIMULATED LUNG FLUID

Simulated

Lung Fluid

Salt SLFC

KC1 0.004

NaCl 0.145

HgCl2 0.001

NH4C1 -

NaHC03 0.024 Glycine

L-Cysteine -

NajCitrate 0.0003 Na Acetate 0.007

CaCU ft (\CiOt

0.0005 0.001

ABOC? aAqueous solution. bEi8O. cKal79, De82. Oiethylenetriaminepentaacetic acid, not present in blood serum. eAlkylbenzyldfmethylammon1um chloride, an antibacterial agent not present in blood serum. TABLE 6-2

SOLUBILITY OF THORIUM DIOXIDE FROM FACILITY B IN

SIMULATED LUNG FLUID

DISSOLVED CONCENTRATION IN Bq/L Day Gross a Uranium Ra 224

1 0.123 0.167 63 3 0.032 0.167 35 10 0.027 0.167 18.3 30 0.045 0.150 12.2 TABLE 6-3

SOLUBILITY OF THORIUM IN THORIUM DIOXIDE FOR

FACILITY B IN SIMULATED LUNG FLUID

Dissolution Rate As Fraction of Undissolved i Day mBq/d per day i 1 37.0 9.8 x 10"6 3 9.6 2.6 x 10"6

10 8.1 2.2 x 10"6

30 3.5 3.6 x 10"6 TABLE 6-4

SOLUBILITY OF RA224 IN THORIUM DIOXIDE FROM FACILITY B

IN SIMULATED LUNG FLUID

Dissolution Rate As Fraction of Day Bq/d Undissolved per day

1 18.9 0.0084

3 10.5 0.0047

10 5.5 0.0024

30 3.7 0.0016 TABLE 7-1

FACTOR USED IN PATHWAY ANALYSIS CALCULATIONS

food crop adult Radioisotope concentration dose factors factors

Th 232 5 x 10~A 1.1 x 10~A

Ra 228 4 x 10~2 2.6 x 10~7

Ac 228 1 x 10~3

Th 228 5 x 10~A 1.5 x 10~5

Ra 224 4 x 10~2 9.3 x 10~8

(1) Bq/g fresh food per Bq/g dry soil from Ss57

(2) committed effective dose equivalent Sv/Bq from Jo83 2 (CCM INUED 1 HE L150«: 03-01*162 T TYPC REACTORS ARE CCNSIUffiED. WHICH A L tic TAKEN IMC Tl CAPABILITIES OF THERMAL BREEDER t-EAC ORS IN SAVING THE ACCOUNT »HEN CALCULAT ISO THfc NATjfiAL IUM EQUIP. MENT S NATURAL URANIUM RESOURCES. FOR DIFFERENT BEAC^CK STRATEGIES. IS C CNCLU CEC HAT AN (IN RUSSIAN). VOZMCZHhCSTI TEPLCVVKH BEAKTOwOV- INPROVED BEACTCR STRATEGY DEVELOP [N It- E HAZMNOZHtTELEJ V EHKCNCMII RE5URS0V PRIRQDNOGO UP ANA, E OF THEE COMBII f"*f T ICICN CCFF KKC HE hEA GAEVSKlJ. 1*1*; SMIRKCV. VU.V. THE FOmR REACTOR U»UR TYPC ITH V CYCL NU I SSN 03?0-<3326. NUCLEAR POWER INOfcPENOENT U The ruw*L URAM PU *T. TEKM, RUDE ?H0H. U9S2). (NC.2 ) P. 3-10. HE SERVES. FU&THER IKPhCViNG IN Tl BREEDING RATIO; CAKPU TYPE REACTCBS; DIAGRAMS: T Uf- T Y PË RE CTCR3 SHOULD NOT BE DELAYED. THE hfiW CAM;L - Th- K ACTCR FORECASTING; L»e» TYPE GEACTCRS ; »QLTEN SALT CCCLZD CONCEPTS ARE "GST PPtF EPA PL f- CO» ^e v re PEACTORSï MOLTEN SALT FUELED REACTORS: PLUTONIUM RECYCLE: NATURAL URANIUM H&SCLRCE SA PC I THORIUM CYCLE ING. THE RESULTS OF INVESTIGATING THE POSSIBILITY CF THERMAL BREEDER »EACTOR ITËR) IKTRCOUCTICN INTC NUCLEAR PCwEfl IN THE NEAREST FUTURE ABE REVIEWED. THE MAIN CHARACTERISTICS OF THE *OST PROMIS ING TBR CONCEPTS ARE PRESENTED. N*ME|_Y, THE MS8R REACTOR (MCLTEN SALT MIXTURES ON THE RASE OF LI. HE. TH. U FLUORIDES ARE USEO AS A CCOLANT ANO A FUEL AS «ELL I ; THE MWSR PEACTCB (FUEL PARTICLES WITH TH02 ANO UC2 ARE 01SPERSEO IN A HEAVY te*TER CCOLANT BEING ALSO A MGOFRATQC I ; THE CANDL-TH. RgACTQK » I TH THCB1UM FUF.L CYCLE; THE Lfcflfl REACTOR (FRESH «AÏE" CCCLEC AND MODERATED REACTOR». CHARACTERISTICS CF THE FUEL CYCLE FCH DIFFERENT 000032

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o 3 z vi ex o s L5 Q^ 1 x o ** a uj ^J uj UJ UJ * f^j aZu ifl-OZ—D 61 61 (CCNTINUEDI RE - L1501: «3-001196 VARIES CEPEN01NG CN THE LEVEL CF ACT1V1T1 IN ThE HOME. E. Tl - » STUDY OF INDOOP AERCSCL SIZE DISTRIBUTION AND G. SMOKING AND COCKING. ThE AVEHAG6 AREA MÊU1AS DIAMETER ATTACHMENT OF RADON DAUGHTERS* FOUND IN THE DWELLINGS HAS 0.2 MUM. A TEChNICUE FCR THÉ AU - JOHANSSON* G*l*ï BCHGARO. M.; NVMAN* S* (LUNO UNIV, f MEASUREMENT OF RACCN DAUGHTER OISTMeuilCN CN 0IFFEPEN7 SWEDEN). DEPT. OF NUCLEAR PHVSICS); AKSELSSON. R. (LUND AIRBCRNE MATTER «AS OEVELCPEO AND TESTEC. Tl-E METhOO IS UNIV. (SVEDENI. DEPT. CF NUCLEAR PHYSICS; LUND UNIV. ( BASED ON THE USE CF AN ELECTRICAL «OeiLllY ANALY/EC ANC SWEDEN). OEPT. Or ENVIRONMENTAL HEALTHi: PGTERSSON, H.; ALPMA-SPECTRCMETRY DF THfc RADON DAUGHTERS COLLECTED ON A SAMUELSSON. C. (LUND HOSPITAL (SwEOEN). RADIATION PHYSICS FLUOROPORE FILTER. SCVE RESULTS APE PRESENTED AND DEPT.). 3859400; 3854400; ; DISCUSSEO. (AUTHOR). NU - ISSN 0021-9502. PU - J. AEROSOL SCI. (19831. V. I«I3) P. «55-458. CO - AEROSOLS IN SCIENCE. VEOICINE ANO TECHNOLOGY. 10. ANNUAL CONFERENCE OF THE ASSOCIATION FOR AEROSOL RESEARCH ( GESELLSCHAFT FU6R AERCSCLFCRSCHUNGI• BOLCGNA (ITALY). | 4- 17 SEP 1982. K£ - AIR: ALPHA SPECTROSCOPY: BUILDINGS; DAUGHTER PRODUCTS; DISTRIBUTION; ENVIRONMENT; FILTERS; MOBILITY; PARTICLE SIZE: RADIOACTIVE AERCSOLS: RADIOACTIVITY; RADON; SAMPLING; VARIATIONS: VENTILATION AS - THE PARTICLE SIZE DISTRIBUTION IN 11 OIFFERENT DWELLINGS WAS STUDIED DURING S TO T OAVS. SAMPLES BEING TAKEN EVERY IS MIN. LARGE VARIATICN IN THE AERCSOL CONCENTRATION HAS BEEN FOUND. ALSO THE ÏIZE DISTRIBUTION OF THE AERCSOL

82 82 (CCNTINUEOI RE - L1423: 83-802946 ALSO BE USED TC ESTIMATE THE POTENTIAL ALPT-A ENERGY Tl - RADON DAUGHTER CAROUSEL: AN AUTOMATED INSTRUMENT FOR CONCENTRATION CF 22ORN OECAY PRCOUCTS. THE DEVICE MEASURING INDOOR CONCENTRATIONS CF 21BPO. 214PB. ANO OPERATE: UNDER THE CCNTRCL CF A CCMPUTER CR A CATA 21181. TERMINAL ANO FUNCTIONS FCR WEEK-LONG PEC IOCS BETWEEN AU - NAZAROFF. W«W* (BUILDING VENTILATION AND INOOOR AIR FILTER CHANGES. THE USES CAN SPECIFY THE SAMFLING— AND QUALITY PROGRAM. LAWRENCE BERKELEY LABORATORY* UNIVERSITY COUNTING-INTERVAL TIMING CVES A WIPE RANCE AND SELECT OF CALIFORNIA, BERKELEY. CALIFCHMA 94720). FROM AMCNG SEVERAL OPERATING MCOES. A NUMBER CF NU - ISSN 0034-6740. PERFORMANCE TESTS ARE ALSC DESCRIBED INCIC'TING THAT FCR PU - REV. SCI. INSTRUM. (SEP 1983). V. 54(9) P. 1227-1233. TYPICAL INOOCR CONCENTRAT 1CN E THE MEASLFEMENT LNCEFTAIMY HE - ACCURACY: AIR POLLUTICN; ALPHA DETECTION; ALPHA IS DOMINATED BY CCUNTING STATISTICS. SPECTROSCOPY: AUTOMATION: BISMUTH 214; CONTROL; FILTERS; LEAD 214: MICROPROCESSORS: MONITCRING; OPTIMIZATION: POLONIUM 218: OUANTITY RATIOS RADON : RADON 220; RADON 222 AS - A MICROPROCESSCR-CCNTROLLED INSTRUMENT FOR MEASURING THE CONCENTRATIONS OF RAOCN PRCGENY IN INDOOR AIR IS DESCRIBED* THE MEASUREMENT TECHNIQUE IS BASED ON ALPHA SPECTROSCOPY AND USES T»0 COUNTING INTERVALS FOLLOWING A SAMPLING PER 100 DURING (HICH RADCH PROGENY ARE COLLECTED ON A FILTER. THE COUNTING INTERVALS ARE SELECTED TO PROVIDE OPTIMAL PRECISION FOR MEASURING 222RN PROGENY FOR FIXEO TOTAL MEASUREMENT TIMES RANGING FROM 30 TO 60 MIN! CONCENTRATIONS AS LOW AS 0.5 BC1/I CAN EE MEASUREO WITH LESS THAN 20X UNCERTAINTY IN 45 VIN. THE INSTRUMENT CAH

84 84 (CONTINUED) RE - L1423: 83-902337 LIVED DAUGHTERS, SCME CF WHICH ARE ALFI-A-P ART ICLE Tl - SAMPLING MINE ATMOSPHERES FOR POTENTIAL ALPHA ENERGY DUE EMITTERS» AND CAN PCSE THE SAME HEALTH hAfAfiC (LUNG TO THE PRESENCE OF RAOON-220 (THORON) DAUGHTERS* CANCER) AS HAS BEEN ATTRleuTEO TC EXCESSIVE EXPOSURE TO AU - ROCK, R.L. RADON DAUGHTERS. THIS PAPER DESCRIBES ThE CECAY OR - MINING ENFORCEMENT ANO SAFETY ADMINISTRATION, DENVER, CO CHARACTERISTICS OF THORCN ANC ITS CAUGhTERSi AND GIVES A (USA). DENVER TECHNICAL SUPPORT CENTER. 9S0B295 SIMPLE FIELO METHCO FCR TESTING FCk ThE PRESENCE OF NU - MESA-IR 1015. THORON DAUGHTERS. WHERE SUCH A TEST PRCVES PCS1TIVE. ThE PU - 1975. 17 P. PROCEDURE FOR DETERMINING POTENTIAL ALPHA ENERGY (WORKING NO - AVAILABLE FROM NT|S, PC A02/MF AOI AS 0E83902960. LEVELS) FRCM THCRCN DAUGHTERS IS GIVEN. ThE CCCURHENCE OF KE - AEROSOL MONITORING; AIR; AIR SAMPLERS; ALPHA OETECTION: THORCN (RADCh-220) AND RACCN (RAOCN-222 I DAUGHTERS DECAY: MEASURING METHODS; MINES; MINING; RADIATION TOGETHER COMPLICATES ThE PROBLEM CF COMPUTING THE WORKING HAZAROS: RADIATION MCMT0R1NG; RACON 220; RADON 222; LEVEL ATTRIBLTABLE TC EACh OECAY SERIES. A SYSTEM IS SAMPLING; THORIUM 232: UBAMUM MINES GIVEN FCR. DETERMINING IF A MIXTURE CF ThCPCN AND RADON AB - ALTHOUGH THORIUM MINERALS ARE NOT COMMONLY FOUND WITH OAUGHTERS IS PRESENT. ANC THE METhcC FCC CCXFUTING ThE URANIUM MINERALS MLNEO IN THE UNITED STATES, THE MINERAL TOTAL POTENTIAL ALPHA ENERGY f CH SUCH M«TLKES IS COMBINATION HAS BEEN CBSERVED IN A FEW DEPOSITS. THE DESCRIBED. POSSIBILITY ALSO EXISTS THAT THCRIUM MINERALS MIGHT BE ASSOCIATED WITH NONUKAMUM ORES CR THAT THORIUM MAY BE A CONSTITUENT OF THE RCCKS SURROUNDING N0NRAD IOACTIVE ORE DEPOSITS. THORIUM-232, LIKE UKANIUM-236, IS THE PARENT OF A DECAY SERIES WHICH INCLUDES A DENSE RADIOACTIVE GAS. IN ThE TnnRlUX SERIES TUS GAS ( CADCN-22 0) IS COMMONLY CALLED THORON. THORCN HECAYS THRCUGh A SERIES nF SHORT- 000022 ***- mm.,

95 96 Kf - Ll»22: BJ-799J50 1 Tl - CALIBRATION ACTIVITIES CONCERNING RAOCN ANO RAOON Tt - PILOT STUOy FOP NATURAL RACIATION SufivEv. IRADCN-222. DAUGHTERS IN AIR. TERRESTRIAL ANO CCS*IC P «0 I AT I ON Is HCKES.I (IN SwEOrSMI. KALISREKINGSVERKSAMHET. RAOON OCH Au - URC«N, L.; ORIECCLL. C K.H«; GREEN, e. y . F . ; PILES, j.c.h RADONDOETTRAR t LUFT. (NATIONAL RADICLCG1CAL PI.CTECT ION eOAKC, h*R»ELL ( UK M * «U - FALK. R.; HAGBERG. N.; fAAKANSSON, B.! NVBLOM, L.: 45C2700 SwEDJEMAPK. G.A. NU - ISSN OJOS-4272. OR - STATENS STRAALSKYDDSINSTITUT. STOCKHOLM ISWEOEN). 5966500 PU - HAOIOL. PROT. BULL. (MA T IV83|. (KC.S2 > P. 16-20. «U - SSI-A 82-22. KE - AIR; BACKGROUND HADIATI CN; BUILDINGS: CCSKÎC RADIATION; PU - 1 5 »AR 1983. 32 P. NATURAL RADIOACTIVITYJ GAÛ1A71CN fCMTChlhC; RAOCh 222 KF - AIRt CALIBRATION STANDARDS: INTERLABORATORY CCMPARISONS; AB - NBPB'S NATIONAL SURVEY CF KATOBAL RACI AT ICN EXPOSURE IK MEASURING INSTRUMENTS: PAOIATION DETECTION; RADON: RAOON HOMES COMMENCEO IN HES AND «ILL RL.N UTIL 198*. A PILCT ISOTOPES SURVEY »AS UNDERTAKEN I h CVEfi 100 HCMES FCP CNE YEAR, A» - THE INSTITUTE MAS ACTEO AS AN INOFFICIAL REFERENCE USING PASSIVE THEROCLU» DESCENT DCSEME1EWS TC HEASU&E LABORATORY AND HAS PUT ROOMS KITH DEFINED CONTENTS OF EXTERNAL RADIATION FRO** TERMESTRIAL ANC CC£WJC SOURCES RADON AND RADON DAUGHTERS AT THE DISPOSAL CF THESE ANO PASSIVE RAOCN OCSE ET EPS TC MEASURE THE KACON-222 GAS CONCERNED. THE STANDARDS, THE «OCXS ANO THE E0U1PMENT ARE CONCENTRATION. A PRELlb INARV ANALYSIS CF Tf-E RESULTS DESCRIBED. THE APPLIED CALIBRATION TECHNIQUE IS REPORTED OOTAINEO PRCM THE PILOT SURVEY IS GIVEN. lue *At* VALUE AND THE RESULTS FRCN INTERKATICNAL INTERCCMPARISONS ARE OF THE PILOT SURVEY »A« IN PKCVIOINC E>PEf^IENCE -KC "RESENTED. (G.R.I. VARIOUS ADMINISTRATIVE AND SCIENTIFIC FRCCEOURES HAVE BEEN SIMPLIFIED OR AUTC MATED FCO ThE NATICNAL SUKVËY. ( U.K. I .

1005 loos (ccNTiNueo) RE - L1221: 81-632279 TI - MONTHLY VARIATIONS OF THE CONCENTRAT 1CNS OF RADON ANO OF RAOON IN THE OPEN ATMOSPHERE. THORON IN BENGHAZI ATMOSHPERE. AU - [SLAW, O.S.: EL BAKKUSH. M.I. (UNIVERSITY OF GARYOUNIS. BENGHAZI (LIBYAN ARAB REPUBLIC). DEPT. OF PHYSICSI. NU - ISSN 013A-0719. PU - J. RAD1OANAL. CHEM. (19911. V. 63(11 P. I77-IS6. NO - » HEFS. «t£ - BETA DETECTION; EXPERIMENTAL DATA; MONTHLY VARIATIONS: QUANTITY RATIO; RADON 220; RAOON 222! SAMPLE PREPARATION; SURFACE AIR AB - THE CONCENTRATION OF THE DECAV PHCOUCTS OF RADON ANO THORON IN THE SURFACE LAYER OF THE ATMOSPHERE HAS DETERMINED IN BENGHAZI FRO» SEPTEMBER. 197S TC MARCH. 1979 EMPLOYING A FILTRATION METHOD ANO BETA-COUNT ING. AN ACTIVITY OF THE ORDER CF 10-15 Cl/L HAS BEEN ESTABLISHED. THE MAXIMUM MONTHLY RN CONCENTRATION OCCURRED IN CECEMBER (THE MINIMUM IN FEBRUARY). THE MAXIMUM THB CONCENTRATION «AS OBSERVED IK JANUARY (THE MINIMUM IN MARCH). THE CONCENTRATIONS WERE FOUNO TO BE PAXIMUM DURING CALM (MILD «INOI AND MUMI0 WEATHER ANC MINIMUM DURING OUST STORH. IN ADO1T1ON. THE MEAN CONCENTRATION OF RN WITHIN THE LABORATORY WAS FOUND TC BE TWICE THE MEAN CONCENTRATION

1010 RE - L1221: 81-632169 Tl - IMMOBILIZATION OF U-TH-RA |M MINE WASTES. AU - BROWN. J.R.; FVFE. W.S.: MURRAY, F.i KRCNBERG. B.I. ( UNIVERSITY Or WESTERN ONTARIO» LONDON* CNTARIO (CANAOAI. DEPT. OF GEOLOGY). 6536280 NU - ISSN 0008-«»92. PU - CAN, MIN. J. (MAD 19SII. V. 102(31 P. 71-76. KE - CONTAMINATION; ELLIOT LAKE: LEACHING; RADIUM; SOLID WASTES: SULFATES; THCRIUM; URANIUM; URANIUM MINES; WATER POLLUTION; APATITES: CONTAINMENT : PHOSPHATES; RAOIOACTIVE WASTE PROCESSING AB - AT PRESENT URANIUM KILL TAILINGS AT ELLIOT LAKE ARE TREATED BY SULFATE PRECIPITATION OF URANIUM, THORIUM ANO RADIUM UNDER STRONGLY ALKALINE CONDITIONS. AS THE PYRITE IN THE TAILINGS IS 0M01ZE0. HOWEVER, THE RAOIOACTIVE ELEMENTS ARE SCLUBTLIZEO. GIVING RISE TO COUBTS ABOUT THE LONG-TERM EFFECTIVENESS OF SUCH TREATMENT. IT IS SUGGESTEO THAT PHOSPHATES MAY PRCVE USEFUL IN IMM0UIL1ZING URANIUM, THORIU". AND PARTICULARLY RAOIUM, SINCF APATITE IS HIGHLY RESISTANT TO WEATHERINO. (LLI. 1074 102* (CCNTI SUED t ME - LI220: 81-629314 CONTENT CF MIES INCCEASEC. THE ZZtkh/ 22SHA I.ATIC IN Tl - RADIUM CONTENT AND THE 226HA/228RA ACTIVITY RATIO IN THE DRILLED «ELLS VARIEO FROM 0.3 TC 2t. *dNCR*ALLY HIGH GR0UNDW4TER FRO" BEDRCCK. 226RA/22SRA RATIOS >ES£ FCuNO IN AREAS illh KNC»N OHANIU» «U - ASIKAINEN. M. (INSTITUTE OF HAD1ATICN PROTECTION* DEPOSITS AS BELL AS IN SEVEHAL DBlLLEC «ELLS AT CTl-ER HELSINKI (F1NLAN0)). 32S9005 LOCATIONS. IN SAMPLES «ITH A LO» RAD ICAC I 1 V IT Y LEVEL THE NU - ISSN 0016-7037. AVERAGE 226RA/228RA RATIO Its SLIGHTLY BELC» UNITY. DU - GEOCHlM. COSMOCMIM. 1CTA. (AUG 19811. V. «5(61 p. 1375- CORRESPONDING TO Tt-E TYPICAL U/TH tATIC CF OG1KITE, Tt-E 1381. MOST COMMON KIND CF ROCK Is THE STUOY AREA. (ALThCfi|. KE - BCPEHOLES: CHEMICAL CCMPOSITION: CORRELATIONS; FIM-AND: GROUND WATER; ISOTOPE RATIO; aUAKTITATIVE CHEMICAL ANALYSIS; RADIUM; RADIUM 2ge; RADIUM 228; ROCKS; WELLS AB - THE RELATIVE ABUNDANCE CF 226RA AND 228RA WERE DETERMINED IN THE GRCUNDWATER FRCM 125 DRILLED HELLS CONTAINING FROM < 0.1 TO 51.3 PCI/L CF 226RA. THE DETERMINATION CF 228CA WAS CARRIED OUT WITH « LIOUIO SCINTILLATION COUNTER BY MEASURING ONLY THE WEAKLY ENERGETIC BETA PARTICLES EMITTED FROM 22SRA. THUS THE INTERFERENCE FROM THE DAUGHTER NUCLIOES OF 226RA WAS AVOIDED. HITHOUT SPECIFIC SEPARATION OF 22BAC. THE CONCENTRATION OF 2J8RA »AS FOUNO TO BE INDEPENDENT OF THE AMOUNT OF 226RA PRESENT IN THE SAMPLES. THE CONCENTRAT ICNS OF 228RA WERE NEARLY THE SAME OVER THE «HOLE RANGE OF 226BA CONCENTRATIONS AND THE AVERAGE 226RA/228RA RATIO SHARPLY INCPEASED AS THE 226RA

1026 1026 (CCNTINUED) RE - L1220: 80-629250 SPECTROSCOPY. TI - GEOCHEMISTRY OF RADIOACTIVE ELEMENTS AND GOLO OF BAIKAL REGION. (IN RUSS1AN1. GEOKHIMIYA RADIOAKTIVNVKH EHLEMENTOV 1 20L0TA 2ABAJKAL*YA. AU - KRENDELEV. R.P. (ED.). PU - NOVOSIBIRSK. NAUKA. 1979. ISO P. NO - 127 REFS.; «7 FIGS.: 46 TABS. KE - GAMMA SBECTROSCO^Y ; GEOCHEMISTRY; G .'LO ORES; IGNECUS ROCKS: ISOTOPE RATIO- POTASSIUM: PROSPECTING: SAMPLING: THORIUM; URANIUM; WATER AB - GEOCHEMISTRY OF GOLO AND RADIOACTIVE ELEMENTS IN MAGMATIC. ORE AND HVPERGENE PROCESSES IS DISCUSSED BASED ON THE DATA FOR BAIKAL REGICN. TECHMOUE CF SAMPLING, PROCESSING AND ANALYSIS OF ROCK. ORE AND NATURAL WATER SAMPLES FOR RADIOACTIVE ELEMENT AND GC1.0 CONTENTS IS CONSIDERED. SPECIAL ATTENTION IS PAID TO THE FEATURES OF GOLO AND RADIOACTIVE ELEMENTS DISTRIBUTION IN INTRUSIVE AND IGNEOUS ROCKS. APPLICABILITY CF BACKGROUND CONTENT VARIATIONS OF URANIUM. THORIUM AND POTASSIUM AS WELL AS THEIR RATIOS IN ENCLCSING AND METASOHATIC ROCKS. IN ORES AND ORE-EXPLOSIVE SYSTEMS FOR MINERALIZATION PROSPECTING WITH THE HELP OF TERRESTRIAL AND AERIAL GAMMA

1035 "E - LI2I9I «1-626740 Tl - INTEGRATED STUDY OF ThE BEHAVIOR OF TRANSURANIC ELEMENTS IN THE MARINE ENVIRONNENT. AU - CHOPPIN, G.R.; MORSE. J.W. OR - FLORIDA STATE UNIV.. TALLAHASSEE «USAI. DEPT. OF CHEMISTRY; MIAMI UNIV., FL (USA). RCSENSTIEL SCHOOL OF MARINE AND ATMOSPHERIC SCIENCES. 2*94000; 4109400 NU - 006/EV/I0306--Tl,; CRC—0306-01. PU - 1981. 23 P. NO - AVAILABLE FROM NT IS.. PC A02/MF A01. KE - ALGAE: AMERICIUM 241 ; AQUATIC ECCSYST6MS: CALCIUM CARBONATES: CATIONS; CORALS, EXPÉRIMENTAL OATA; MATHEMATICAL MODELS; NEPTUNIUM: PLUTONIUM: RADIONUCLIOE MIGRATION; SEOIMENTS; THORIUM; UPTAKE: URANIUM OXIDES AB - IN ORDER TO CONSTRUCT A MODEL OF RADICNUCLIOE KINETICS I» AN AQUATIC ECOSYSTEM, AVERICTUM IONS WERE CHOSF.N FOR STUDY, RESULTS WILL BE APPL1EO TC THORIUM, PLUTONIUM. NEPTUNIUM AND URANIUM FCR CCMPAR1S0N CF ENVIRONMENTAL OEHAVICR. 1036 1038 (CCKT1NUFOI «H - L12I9! 81-626732 SEDIMENTS INDICATE: 11) A NORTHERLY TRANSPORT CF SUP(226) II - ANOMALOUS ISOtOPIC ACTIVITY RATIOS IN TERRESTRIAL RA LEACHEO CUT OF THE SEDIMENTS CF THE "CNAilTE REGION CF ENVIRONMENT• KECALA «NO CfcCAY CF SUP(228IRA TO SUP(22flTH DURING ITS AU - J05HI. L.U.; MISMBA. u.c. (BHABHA ATOMIC RESEARCH CENTRE. NORTHERLY TRANSPORT. (2) FkAÇTICNATION EET»EEN SUP(2361U BOMBAY (INDIA). AIR MCN1TORING SECTION). 0807100 AND SUP(234)U PUT NO FRACT 1ONATI ON PETBEEN SLP(238>U ANO PU - BULL. MAD1AT. PROT. {JAN - JUN 1980). V. 3(1-2) P. 17-21. SUP(235)U. (3) A NCBTHEBLV TRANSPORT ce SUPI234IU AND ITS NO - 7 REFS. DECAY TC SUP<230)TH DURING TRANSPCBT. ASC III TRANSPCKT CO - 7. INDIAN ASSOCIATION FCR RAOIATI0N PROTECTION CONFERENCE OF SUPI234IU FRCM REGICNS CF UEAMU» CCI-CE M I: AT 1CNS TO ON RAOIATÎON ENVIOCNKENT IN LIFE AND EARTH SCIENCES. TME AREAS CF HCT SPRINGS ANO KHARI R IV E F. . <*.G.O.I. 8AR00A. IKDIA. 25 - 27 FEB 1980. KE - COASTAL WATERS; GEOCHEMISTRY: INDIA; ISOTOPE RATLC; RIVERS; SEDIMENTS; SMCHES: TMOBIUM 228; THORIUM 232: THORIUM 230: URANIUM 234; URANIUM 238: URANIUM 235 AB - GEOCHEMICAL BEHAVIOUR OF SUPI228ITH. SUPI230ITH. SUP(232) TMI SUP(2341U. SUP(235)U AN0 SUP(Z3B1U IN THE COASTAL MARINE SEOIMENTS ON THE WEST COAST CF INDIA FFLOM BOMBAY TO KAVAMKULAM AND IN THE SEDIMENTS OF HOT SPRINGS ANO KHAR! RIVER IN THE TUWA REGION IN THE PANCHMAHAL DISTRICT OF THE GUJARAT STATE HAS BEEN STUDIED. VARIATIONS IN THE ACTIVITY OATIOS OF SUP(228ITN/SOPI232)TH, SUP(230)TH/SUP< 232JTH, SUP<23«)U/SUP(?3A»U ANO SUPI23S)U/SUP<23»)U OBTAINED FOR COASTAL MARINE SEDIMENTS AND THOSE OF SUP< 234IU/SUPI238ÏU OBTA1KEO FOR HOT SPRIKG AND KHART RIVER

1031 1040 BE - L12I9Î 81-6215721 P0 - L1219: ej-c2t7oe TI - MEASUREMENT OF NATURAL RADIOACTIVITY CONTENT OF SEA-BED. Tl - SOIL ANO VEGÊTATICK. AU - SADAStVAN* S. (BHABHA ATOMIC RESEARCH CENTRE* BOMBAY < AU - ANON. INDIA). AIR MONITORING SECTION). 0807100 SUL*. M.J.: eLUMER. P.J. PU - BULL. RADIAT. PROT. (JAM - JUN 1480). V. 3(1-21 ». 3-6. CP - OATTELLE PACIFIC KCRTM*E5T L *DS. . M CML ANO . * A < USA) . NO - 8 REFS. 9500022 CO - 7. INDIAN ASSOCIATION FOR RADIATION PROTECTION CONFERENCE NU - PNL — 37 £6. ON RADIATION ENVIHCNMENT IN LIFE ANO EAflTH SCIENCES. PU - P. 29-31. ENVIRONMENTAL SURVEILLANCE AI t-iSFC>0 FCR CV- BABOOA. INDIA. 25 - 27 FEB 1980. 1960. APR 1961. KE - CALIBRATION STANDARDS; EXPERIMENTAL DATA: I NO IA : LI- KË - CESIUM 13*; CESIU* 137: FALLCUT; HANFÇGC RESERVATION; OP1FTED GE DETECTORS: NATURAL RADIOACTIVITY. POTASSIUM NATURAL RADIOACTIVITY; PLANTS; PLUTChlU"; POTASSIUM 40. 40; RADIOMETRIC ANALYSIS; SEA BEO; SEDIMENTS! TMOHIUM; RADIATICN MONI TOR[NG ; RACICNUCLIOE MiGPATICN; PAD I LM 2 2*; URANIUM RAOIUM 226: SAbPLIhG. SCILS; STRCNTIUH 90; USAMUM; AB - A STANDAROAROISED MEASUREMENT PROCEDURE FCB ANALYSIS OF ZIRCONIOM 9* U. TH AND 40K IN SCIL SAMPLES USING A HIGH BESOLUTION CE( AS - SURF ACE SOIL ANO VEOETATICN SAMPLES ARE CCLLECTEO LI) DETECTOR IS DESCRIBEO. THE RESULTS OF ANALYSES OF A ANNUALLY FRCM A NUVGER CF LGCATICNS FCR THE PUKPCSE CF NUMBER OF DEEP CORE SCIL SAMPLES COLLECTED AT DEPTHS MEASURING THE KA0ICNUCL1DE CONCENT AT1CNE FROM RANGING FROM 2S0 M TO 2500 M FROM AN OFF-SHORE WEIL ARE FALLOUT. NATURAL CAUSES* ANO ANY C MULATIVE eUlLOUC CF PRESENTED. (K.M.). RADIONUCLIOES FROM HANFCRD 0PERAT1 NS. BADICKUCL1QE CONCENTRATIONS IN SAMPLES TAKEN OU ING l«ec »ERE SIMILAB TO PREVIOUS YEARS. >>C OBVIOUS GECG APHICAL RACIONUCLIOE 0I5TRIBUT10N PATTERN *AS OBSERVED N IKE itbO SAMPLES.

1044 1044 (CCNT tNUED i RE - L1219! 81-626436 V RATICS ARE LIKEAfc CVEP THE 5- TC 10 0-MLG RANGE OF TI - DETERMINATION OF ULTRATRACE CONCENTRATIONS OF URANIUM ANO INTEREST* ANO THE DETECTICN LI«IT CF EACH ELEMENT CN THE THORIUM IN NATURAL WATERS BY X-RAY FLUORESCENCE. FILTER DISK ( S Z MUG (J SIGMA). RELATIVE STANDARD Au - STEWART. J.H. JR.; 6BC0KSBANK, R.O. OEVIATICN kAS I7X AT THE 1&-NUG *SC *X AT THE 10&-MUG UR - OAK RIDGE NATIONAL LAP.. TN (USA). 4832000 LEVEL FO« THORIUM ANO 1IX AT THE II-MUG ANC 2% AT THE NU - C0NF-8I0647 6. 10 0- MUG LEVEL FOR URANlu». ANAL Y S IS Cf- SPIKED SOLUlICNS PU - 1981. 9 P. SHOWED A PECCVEPY CF 1Ç.6 •- 0«3 fLG FCB UCANlUM AND lî.e NO - AVAILABLE FROM NT1S*. PC A02/MF A01. •- 0.3 MUO FOB THORIOM AT THg 20-MLG LEVEL. AhC THE CO - CONFERENCE ON X- ANO CAKMA-HAY SOURCES ANO APPLICATIONS. NCRMAL LCtaEP. REPORTING LIMIT IS S *-UG. FIFTY DISKS CAN HE ANN ARBOR. ML. USA. 10 - IS JUN 1981. ROUTINELY MEASURED 2'J'J ! KT, A NORMAL «CRKING DAY. KE - ACCURACY; AOUEOUS SOLUTIONS: CALIBRATION STANOACDS; COPRECIPITATION: GROUND WATER: SURFACE WATERS; THORIUM; TRACE AMOUNTS; URANIUM: X-RAY FLUCRESCENCE ANALYSIS AB - AN X-RAY FLUORESCENCE METHCO FOR THE SIMULTANEOUS DETERMINATION CF URAMUM ANO THCB1UM AT THE LESS THAN I PPM LEVEL IN NATURAL WATERS IS DESCRIBEO. URANIUM AND THORIUM AFLF CCPRECIPITATED WITH AN INTERNAL STANDARD* RTTOIU". ANO INCORPORATED INTO AN IRON-ALUMINUM HYDROXIDE CARRIER. THF. HYOOOXIOE PRECIPITATE IS FILTERED. ANO THE FILTER DISK IS ANALYSED BY THE ENERGY-0ISPERSIVE X-RAY FLUCRESCEFCCE TECHNIQUE. MATRIX INTERFERENCES CAUSED BY TM€ PRESENCE OF UND^EC ICTAOLE ANICNS AND CATIONS ARE COMPFNSATED FOB BY ThE INTERNAL STANDARD. THE U/Y AND TH/ 1059 1059 CCCNTINUEU) HE - L1218: 81-624559 TO THE FALL LISE REGICN IN SCUTM CAKCL1NA. Tl - M0HILI7AT10N OF URANIL» ANO TMOfilUM DECAY SERIES ISOTOPES IN THE HYOROLOGIC CYCLE. Au - MICHEL. J. OH - SOUTH CAROLINA UNtV.e CCLUVBIA (USAI. THESIS (PH. D.J. S836000 °U - I960. 113 P. NO - UNIVERSITY MICRCFILNS CKOER NO. 90-20.303. KE - ENVIRONMENTAL IMPACTS: CROUNO WATER; HYDRCLOGV; LEACHING; OXIDATION: BADIOCHEMISTPV: RADIUM 22bî RADIUM P2fl; THORIUM ISOTOPES: URANIUM ISOTOPES AB - TO ASSESS THE EFFECT CF WEATHERING >M) GRCUNO «ATE» LEACHING PROCESSES OK ThE ISOTOPIC FHACT IONATION C URANIUM AND THORIUM SERIES ISOTOPF/S • RAOICCHEMICL STUDIES OF THREE DIFFERENT. THOUGH RELATEO SYSTEMS SERE UNDERTAKEN. THEY INCLUDED: (1) THE ISOTOPIC DISTRIBUTION OF URANIUM, THORIUM. ANO RADIUM THROUGH A WEATHERING PROFILE OF A GRAM2TIC SAPROLITE. USING AN 1SOVOLUMETRIC APPROACH, (1) THE BEHAVIOR OF 226RA ANO 22BRA IN AN AQUIFER COMPOSED OF LEATHERED IMMATURE SEDIMENTS. AND (3) THE EFFECT OF P-ECENT FRCCESSES CN THE REDISTRIBUTION OF URANIUM SERIES ISOTOPES IN URANIFERCUS GORCEIXITE (BA-AL PHOSPHATE). ALL THREE STUOY SITES «ERE LOCATEO ADJACENT 0J0032

106B 1068 (CONTINUED! RE - 11217: 81-621765 SOUTH CHINA SEA. A wAJCf- SOURCE CF Z26RÂ IK ThE INDIAN TI - DISTRIBUTION OF 228RA IN SURFACE SEA MATER CF THE EAST OCEAN MAY RE COASTAL SEDIMENTS OF INDONESIA. THE MIXING INDIAN OCEAN. BATE Of SURFACE «ATEC MASSES ACROSS THE SUSTfiCFICAL AU - OKURO, TAKASHI (KOBE UNIV. CF MERCANTILE MARINE (JAPANM: CONVERGENCE «AS CALCULlTtC BY USING A S1»PLE BCX MCDEL FURUVAMA, KAZUNORl; SAKANOUE, M4SAN0BU. 3630200 BE ABOUT tl KM/Y. (ALTHCR1. NU - ISSN 0016-7002. PU - GEOCHEM. J. JTCKYCI. (NCV 1479). V. 13(5) P. 201-206. KE - OEPTH; EXPERIMENTAL OATA; GAMMA SPECTROSCCPYi iNOlAN OCEAN: OCEANHGHAPHYi CAO10 ACT IV I TY: RADIUM 226; RADIUM 22s: SEA»ATEB; SPATIAL DISTRIBUTION; TEMPERATURE DEPENDENCE AS - THE CONCENTRATIONS OF 22SRA AND 226RA IN THE SURFACE AND SUBSURFACE SEA DATER SAMPLES COLLECTEO FROM THE EAST INDIAN ANO THE WEST PACIFIC OCEAN WERE DETERMINED» RADIUM ISOTOPES WERE ANALYZED EY GAMMA-RAY SPECTRCMETRY OF 226TH MILKING METHOD. SURFACE WATERS CF THE NORTHERN tNOlAN OCEAN TO THE NORTH OF LATITUDE 300S CONTAINED HIGHER CONCENTRATIONS OF 228RA (63-32 OPM/1.000 L> THAN THOSE OF SOUTHERN AREA AND THE WEST PACIFIC OCEAN (LESS THAN 8 DPM/I.000 L). THE SAMPLES FROM NEAR SHORE HATCH OF INDONESIA AND THE SOUTH CHINA SEA SHCWEO HIGH 228HA CONTENTS, 629-164 DPM/1.000 L. THE CONCENTRATIONS CF 22BRA IN SUBSURFACE WATERS WERE VERY LOW EXCEPT FOR THE 000032

1075 1075 (CONTINUED) RE - L1216: 81-61960» WIRE-SCREEN SAMPLE» IS A RELIABLE DEVICE FCR THE Tl - COMPARISON OF THE OIFFUSION CHAMBER ANO THE WIRE-SCREEN ESTIMATION OF UNATTACHED RADON OUJGHTEfS. (S.G.a.l. SAMPLER FOR ESTIMATICN OF UNATTACHED RAOON-OAUGHTERS. AU - KHAN, A.H.; SRIVASTAVA. G.K.; RAGHAVAVYA. M. (BHABHA ATOMIC RESEARCH CENTRE, JADuGUOA (INDIA). HEALTH PHYSICS UNITI. > »U - HULL. RADIAT. PROT. (APR - JUN 19791. V. 2(2) P. 26-30. NO - 6 REPS,. 2 TABLES. CO - 6. IMOIAN ASSOCIATION FCR RADIATION PROTECTION CONFERENCE. BOMBAY. INDIA* 7-9 MAR 1979. KE - AIR SAMPLERS; COMPARATIVE EVALUATIONS; DAUGHTER PRODUCTS; OIFFUSION CHAMBERS: FLCW RATE; PERFORMANCE: RAOON: SCREENS: URANIUM MINES AN - AMONG THE DEVICES AVAILABLE FCR ESTIMATION OF THE UNATTACHED FRACTION CF RAOON DAUGHTERS THE OIFFUSION CHAMOED ANN WIPE-SCREEN SAMPLER ARE USEFUL IN URAN1U" MINES. PERFORMANCE CF THE TWO DEVICES HAS BEEN COMPARED IN LABORATORY ANO THEIR RELATIVE MERITS FCR RCUTINF USE IN MINES HAVE BEEN DISCUSSED. THE EFFICIENCY OF THE OIFFUSION CHAMRER ANC WIRE-SCREEN FCR COLLECTION CF UNATTACHED RADON DAUGHTERS VARY WITH THE RATE OF AIR FLOW THROUGH THE» ANO "CTh THE CEVICES HAVE AN INVERSE RELATIONSHIP WITH THE FLOW RATE. IT IS SHCWN THAT THF 00003? •-m mut,

10 76 10 77 RE - L1216: 81-619592 RE - LI216: 8I-61Ç4Ç? T| - ELECTRET SYSTEM - » NE» APPROACH IN MEASURING RAOCN, Tl - RAPID MEASUREMENTS CF 222£N IN WATEK B» IN blTb GE(LI 1 THORDN AND THE DECAY PRODUCTS IN 0VELL1KG5. SPECTRCWETRY 2. AU - KGTRAPPAt p*î DUA« S*K.: GUPTA, P.C.I MAYYA, Y.S.i NAMflt *U - KOMURA, KAZUHISA; «AXANCUE. MASANCEU i**h*lfi*H UM. ( K.S.V.: BHAGWAT. A.M.; SOMAN, S.O. (OHABHA ATOMIC JAPAN). LOW LEVEL RACI0 ACT IV IT Y LAB.). RESEARCH CENTRE. BCMeAY (INDIA). HEALTH PHYSICS DIV.I. CR - DEPARTMENT CF ATCMIC ENERGY, BCveAY (II-CIM; IKCIAN 0807300 ASSOCIATION FOR RAulATICN PHCTECT1CN, BCOOAY. 2118000; OR - DEPARTMENT OF ATOMIC ENERGY. BOMBAY (INDIA); INOIAN 9700292 ASSOCIATION FOR PA01ATICN PROTECTION. BOMBAY. 211B000; NU - INI S-MF—6S30. 9700292 PU - P. 60. SECOND SPECIAL SVMPCSIU* CN NATLP'L PADIATIC* NU - INIS-MF 6530. ENVIRONMENT (HELD AT» BCFBAY. 19-2J JANUARY 1961: PU - P. 48-49. SECOND SPECIAL SYMPOSIUM CN NATURAL RADIATION ABSTRACTS. BOMHAY. UHABHA ATCMIC BESEAFICK CENTRE. 1981. ENVIRONMENT (HELD AT) BOMBAY* I9-23 JANUARY I9B1: NO - PUBLISHED IN SUMMARY FCRM ONLY, ABSTRACTS. BOMBAY. BHABHA ATOMIC RESEARCH CENTRE. 1981. CO - 2. SPECIAL SYMPCSIOK CN NATURAL «JCIII1» ENVIRONMENT. NO - PUBLISHED ÎN SUMMARY FCRM ONLY. S REFS. BOMBAY, INDIA. 19 - 23 JAN 1

1 085 I08S (CCMlMJtO) RE - L1216: 81-619475 THORON DECAY-PROOUCT CONCENTRA Tl n* Ç |< tfADB EÏ COLLECTING TL - METHODS FOR A CONTINUCUS REGISTRATION OF RADON. THORON. THE AEROSOLS CK A KEMERANE FILT.= R ANC SIMULTANEOUSLY AND THEIR OECAY PRODUCTS INDOORS AND OUTOOORS. COUNTING THE ACTIVITIES BY ALPHA SPEC 1RCSCCPY. THE AU - PORSTENOOERFER• J.I «ICKE. A.: SCHRAUBT A. OECREASE OF t TRACER-GAS CCNCENTR»!ION (CCJ) Is USED TC GESELL. T.F.; (.ODER, W.M. (EDS.), DETERMINE THE VENTILATICK RATE OF A PCC». OR - DEPARTMENT OF ENERGY, CAK RIDGE. TN (USAI. TECHNICAL INFORMATION CENTER. 9505437 NU - CGNF-78V>"!2 (VOL.21. PU - P. 1293-1307. NATURAL RADIATION ENVIRONMENT III. 1980. CO - CONFERENCE ON NATURAL RAOIATION ENVIRONMENT III. HOUSTON, TX, USA. 23 - 28 APR 1

1098 1099 RE - L1216: Al-619033 - L1216: 81-619032 Tl - INDOOR CONCENTRATIONS OF 222RN AND 220RN OESCENOENTS: - RADIOACTIVITY CF BUILDING MATERIALS: ABSCRCEO OCSES. ABSORBr'J DOSES. - GAH20N, L.; FCNTEKLA, C; SUAREZ, A. (CVIECO UNIV. ( AU - GAR20N. L.; FONTENLA. P.: SUAREZ. A. (OVIEOO UNIV. ( SPAIN). ENERGY NUCLEAR OEPT.I. SPAIN). ENERGY NUCLEAR DEPT.I. - DEPARTMENT OF ATOMIC ENERGY. BOMBAY (INDIA); INDIAN OR - DEPARTMENT OF ATOMIC ENERCY, BOMBAY (INOIA); INDIAN ASSOCIATION FCR RAOIATICK PRCTECTICN, CC*e>Y. 2118000! ASSOCIATION FOR RA01AT1CN PROTECTION, BOMBAY. 2ttfl000: 97002»* 9700292 - INIS-MF—6530* NU - INIS-MF 6530. - P. 1J0-123. SECOND SPECIAL SYMPOSIUM Ct. NATURAL RACIAT10N PU - P. 12»-|25. SECOND SPECIAL SYMPOSIUM ON NATURAL RAOIATION ENVIRONMENT (HEL? AT) BOMBAY. 19-23 JANUARY IQfil: ENVIRONMENT (HELD ATI BOMBAY. 19-23 JANUARY I9S1I ABSTRACTS. ECMBAV. BC»BH ATCHIC KESEACCI- CENTRE. 1981. ABSTRACTS* BOMBAY. BHABHA ATOMIC RESEARCH CENTRE. 1981. NO - PUBLISHED IN SUMMARY FOR» CNLV. 2 TABLES. NO - PUBLISHED IN SUMMARY *C« ONLY, 6 REFS. CC - 2. SPECIAL SYMPCSIU» ON NATURAL RADIATION ENVIRONMENT. CO - 2. SPECIAL SYMPOSIUM ON NATURAL RAOIATION ENVIRONMENT. BOMBAY, INOIA. 19 - 23 JAN 1981. BOMBAY, INDIA. 19 - 23 JAN 1981. - BUILDING MATERIALS: BUILDINGS: GAMMA OCSI»ETEY; NATURAL KE - AEROSOLS: AIR: BUILOIKGS: DAUGHTER PROOUCTS: DOSIMETRY; RADIOACTIVITY; POTASSIUM 40: RADIATION OCSES; RAOIUM 22a; LUNGS; NATURAL RADICACTIVITY: RAOIATICN DOSES: RAOON 220: RADON: «PAIN; THCMUM 232 RADON 222! SPAIN; VENTILATION -si»:

3006 3005 WE - L0622: 75-213135 - L0622: 75-213156 - THE CONCENTRATION OF 222RN, 220RN AND THEIR OAUGHTERS IN TI - COMPARATIVE EFFECTS IN HAMSTERS. (.ATS, ANO MICt OF THE AIR, THE DEPENDENCE CN METECBCLCG1CAL VARIABLES AND EXPOSURE TC 5IMULA1EO URANIUM MINE ATMOSPHERES. (RADCN CONTRIBUTION TC THE RADIATION OCSE POP THE INHABITANTS OF DAUGHTERS. ) A RADCN SPA. AU - PALMER. R.F.; FlLlFY. R.E.; STUACT, E.C. - STEINHAEUSLER. F.; PCI-L . E. (RESEARCH INSTITUTE GASTEIN THOMPSON. R.C. OF THE AUSTRIAN ACADEMY OF SCIENCESi BAOGASTEIN (AUSTRIA) CB - BATTELLE PACIFIC NCRTHWEST LAOS.a MCHLAN0. fcASH. (USA). I. 9500022 RUJDOSC. E. (ED.I. NU - ONWL—11S0IPT.il. - HFALTH PHYSICS PROBLEMS OF INTERNAL CONTAMINATION. PU - PACIFIC NORTHWEST LABORATORY ANNUAL REPGBT FOR 1974 TO PROCEEDINGS OF THE 1RPA 2N0 EUROPEAN CONGRESS ON THE EROA DIVISION CF BIOMEDICAL ANC E SV I fCKH EM AL RADIATION PROTECTION CRGANIZED BY THE EOTVOS LORAND RESEARCH. PART I. 61CMED1CAL SCIENCES. »Afc 1975. P* PHYSICAL SOCtLTY. HEALTH PHYSICS SECTION. BUDAPEST. 122-123. AKAOEMlAl KUDO 1573. P. 347-400. KE - AIR; ALPHA SOURCES; BIOLOGICAL HACIATICN EFFECTS; NO S TABLES. DAUGHTER PRODUCTS; OUSTS; HAMSTERS; INHALATION; MICE: CO IRPA 2 EUROPEAN CONGRESS ON RADIATION PROTECTION, MINES; RADIATION HAZARDS: PACON; RATS: URAMLM ORES BUDAPEST* HUNGARY. 3 «AY 1972. AQ - HAMSTERS. RATS. ANO MICE «ERE CHRCMCALL» EXPOSED TO AIR; AUSTRIA; PALNEOLCGY; COMPARATIVE EVALUATIONS: RADON DAUGHTERS. WITH AND WITHOUT URANIUM CRE DUST. TC DAUGHTER PRODUCTS: OCSE COMMITMENTS; INHALATION; IRPA; PROVIDE AN INTERSPECIES CCMPARISCN OF THE EFFECTS CF POPULATIONS: RADIATION DOSES; RACIOACTIVITY; RADON 220: THESE URANIUM M|NE INHALATION HAZARDS. (L.S.I. RADON ?22

3008 3008 (CONTINUED) SF - L0622: 75-212998 OF THE RADON CAUGHTERS 2I4PB AND 214BI WERE MEASURED IN Tl - DETERMINATION OF AERCSCL DEPOSITION RATES ON A L';E THE ATMOSPHERE ANO IN LAKE CRESCENT WATER IN CONJUNCTION SURFACE USING RADON DAUGHTERS. (214PB ANO 214 el TRACERS. WITH WIND SPEEC MEASLREMENTS TC DETERMINE THE RATE OF ) TURBULENT DEPOSITION CF ATMOSPHERIC AEBCSCLS CN THE LAKE AU - YOUNGt J.A. SIMPSON. C.L. SURFACE AS A FUNCTION CF WINO SPEEC. (U.S.I. OR - HATTELLE PACIFIC NORTHWEST LABS.. R1CHL.ANO, HASH. (USAI. 9500022 NU - HNWL--19S0

3018 3019 «E - L0621: 75-2I00Ï2 RE - L. 062 1: 75-2100*1 TI - MAXIMUM PERMISSIBLE CONCENTRATION OF THORIUM 232 ANO TI - MAXIMUM PERMISSIBLE LEVELS OF NATURAL f- AD 1CNUCLI DE S IN NATURAL THORIUM IN CRINKING WATER. BUILDINGS MATERIAL!. (IN RUSSIAN). K OBOSNCVANIYU GlGlENICHESKIKH NORM (SOK) SJIANI TORIYA-232 I TORIYA ESTESTVANNOGC V PITiEVOJ VOOE. ii" ?" « ISSLEDCVAME I NCRMIRCVAME BAC IC A«T I VNC SÏ 1 AU - LYARSKIJ. P.P.! PAVLCVSKAVA, N.A.; PETUSHKOVi A.A.: ZEL* STROITEL'NYKH MATERIALCV. TSEB. M.R.; PR0TOR0V. A.V.; MAKEEVA, L.G. (AKADEMIYA AU - KRISYUK. EH.M.; TAR4S0V. S.I.: SHAMCV. V.F.; SHALAH. N.I. MEDITSINSKIKH NAUK SSSR. MOSCOW. INST • GIGIENV TRUDA I ; LISACHENKC. EH.P.; GOMEL-SKIJ. L.G. (LENINCHADSKIJ PROFESSIOKAL'NYKH ZABCLEVANIJI. 0153000 INST. RAOIATSICNNCJ OIGIENY (USSR)). 3719180 OR - STAATLICHES AMT FUER ATOMSICHERHEIT UMD STRAHLENSCHUTZ, OR - STAATLICHES AMT FUEI\ ATCMS ICHERHE IT UNC STBAhLENSCHUT Z . BERLIN (GERMAN DEMCCEJTIC REPUBLIC). 5905020 BERLIN «GERMAN DEMOCRATIC REPUBLIC). 5905020 NU - SZS--IST. NU — SZ a*"* I S 7 • >>U - RADIATION PROTECTION» EKV1B0NMENT *HD POPIH.AT ICK. PiPEBS PU - RADIATION PROTECTION. ENVIRONMENT ANO FCFULATICN. PAPERS OF THE 1ST SEMINAR. PCTSOAM OCT 16-21. 1972. ( STRAHLENSCHUTZ, UMWELT UNO BEVOELKEBUNG. HATECIALIEN OES OF_f«e 'sr SEMINAC FCTSCAM CCT 16-21. i«7j. ( 1. SEMINARS. POTSDAM 16.-21. OKT. 1972.) MAR 1974. P. 33- STRAHLENSCHUTZ. UMWELT UND BEVCELKERUNG. MATER1AL1EN DES 1. SEMINARS. POTSOAM 16.-II. OKT. I972.I MAR 1474. P. 25- 37. C0 " '•JNTE"NATIONAL SEMINAB CF SOCIALIST CCLNTSIES CN CO - 1. INTERNATIONAL SEMINAR OF SOCIALIST COUNTRIES ON RADIATICN PROTECTION, ENVIRONMENT ANO POPULATION. RADIATION PROTECTICN. ENVIRONMENT AND POPULATION. POTSOAM, GERMAN DEMOCRATIC REPLBLIC. It CCT 1972. POTSDAM, GERMAN DEMOCRATIC REPUBLIC. 16 OCT 1972. KE - BUILDING MATERIALS; HUMAN POPULATIONS: MAXIMUM KE - BIOLOGICAL HALF-LIFE; ORINKING WATER; MAXIMUM PEPMISSIflLE PEBMISSItLE CONCEKTCAT; NAIURAL BAC 1CAC 1 I V IT Yi BACIAT1GN CONCENTRAT; IMC»lu»i THCHIUM 232: USSR DOSES: RADIATION PROTECTION; RADIUM 22ei THCBIUM 2 '2 u < »~ • a: •«

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l I (CCNT I NUED» U150»: 83-0021 M THQRÛN ACTIVITIES IN INCOGS Al K , ThE FCPwATlCN CF F k E E INVESTI CATIONS CN NATURAL RADIOACTIVITY OF INDOOR AIR AND AERCSCL-BCUNO CAuGHTEN PRODUCTS ANC THE Ifi PARTIAL °CLLUT|ON. FUNDAMENTAL F IND ÏNGS S£RVING TC ESTIMATE X- LOSS DUE TO AIR-EXCHANGE AND DEPC51TILN PROCESSES. IRRADlATION BY INHALATICN CF RAOCN- ANC THORON DAUGHTER FINALLY THE CCNTRIBLTtON Ch NATURAL INOCCP fiADICACT1V I IV PRODUCTS. TO THE NATURAL ExPCSU^E TC RADIOACTIVITY CF MAN CRATE CF ( IN GERMAN» . UMERSuCt-UNGEK ZUR FPAGE CER NATUERL ICHEN VENTILATION» IS ESTIMATED CN THE 8*SIS CF THE PRESENTLY RA010AKTIVITAET DER LLFT IN «CHK- UND AUFENTHALTSBAFUMEN. AVAILABLE MEASURING DATA. THIS ESTIWATICN eAiES CN AN GRUNQLAGEN ZUR ABSCHAETZUNG DER STPAMLENEXPCSITION DURCH INVESTIGATION CF THCSE CECHAMSMS. **-ICh APE PESPDNSldLE INMALTION VON RADCN- UNC THCRON-ZERFALLSPPODUKTEN. FOR A CONTINUOUS JLPPLY CF RADCN AND THCF-CK fcr ThE •ICKE. A. BUILDING WALL-MATEPIAL. (CfilG./HP). GIES5EN UNIV. (GERMANY. F.R.). F ACHE»ERE I CH PHYSIK. DISS. (0.SC.)< 9200620 NU INIS-MF—6335. PU 13 DEC 1979. 175 P. KE BODY 6URDEN; BUILDING MATERIALS; EUILCLNGS* OAUGHTËP PRODUCTS; DOSE COMMITMENTS; DOSE RATES; INHALATION; LUNGS ; M(KW; NATUR AL RADIOACTIVITY; PAC1QNUCL \ DE K TNET LC5 ; BADCNÎ RESPIRATION; THORIN; VENTILATICN THE DEHAVIOUR CF RADCN . THC«ON AND THEIR DAUGHTER PRODUCTS IN INDOOR AIR ANC THE CCRRFSPONOING PROCESSES ARE EXPLAINED AND QUANTITATIVELY RECCPOED (AS FAG AS POSSIBLE). MA IN SURJECT CF ALL CCNSIOERATLONS ARE THOSE PROCESSES. WHICH INC'ICE THE OEVELCPMËNT CF RAOCN- ANO 000030

10 10 (CCKT INUED ) HE - LM22Î «3-799068 PLUTONIUM 23SÎ QUANTITATIVE CHEMICAL ANALYSIS; THOHJU* Tl - TO STUDY THE CONCENTRATION OF NATURAL RADI0NUCLIDE5 I 232; TRACE AMOUNTS; URANIU" 2J5; URANIUM 2 20 1 taCMEN URANIUM, THORIUM) ANC CERTAIN TOXIC TRACE ELEMENTS ( HAIR SAMPLES WERE COLLECTED FRCM MALE iNC FE^ALE DCNQRS ARSENIC, MERCURY* AKTIMCNV, LEADI IN HAIR OF PERSONS LIVING IN SELECTED INOLSTPIAL CR AGKICLLTUFAL AREAS OF LIVING IN INDUSTRIAL ANO AGRICULTURAL AREAS OF BYELORUSSIA. SAMPLES »EPE ANALYSED 6Y INAA PCf- AS* HGi PQ BYELOPUSSI4. PART CF A COORDINATED PROGRAMME ON NUCLEAR AND SB, WHILE TH AND U WERE DETEaHNED ev THE SCL IC TRACK METHODS IN HEALTH-TREATED WONITCRING OF TfiACE ELEMENT DETECTOR (STOI "ETHCD. CVEf-ALL. CCKC6N1CAT1CNS OF THE POLLUTANTS* F1NAL REPCRT FCR THE PERIOD 31 0EC£M8ER 1980 ELEMENTS MONITORED »ERE LC» »ITH THE ExCEPTICN CF PB FOR - 30 DECEMBER 1991* WHICH RELATIVELY HIGH CCNCENTRATICNS »EPE CESEPVED IN (IN RUSSIAN). IZUCHENIE 50DERZHAMYA ESTESTVEKNYKH INDUSTRIAL AREAS. KC SIGNIFICANT OIFFEPENCEE IN THE PADIONUKLIOOV (UPANA, TCRIVA) I NEKCTCRYKH TOKSICHESKIKH CONCENTRATIONS CF THE ELEMENTS SURVEYED *EPE CCSEHVEO MtKROELEMENTOV (MYSH'VAKA, RTUTI, SUR'MY, SVlNTSA) V BETWEEN INDUSTRIAL AND AGRICLLTuRAL AREAS NCP EET»EEN VQL.OSAKH ZH1TELEJ • PKCZHl V *tOSHCH 1K.H V PRCMYSHLENNYKH 1 MALE ANO FE*"ALE DCNQBS. SEL*SKOKHOZYAJSTVENNYKH RAJONAKH BELOHUSSKOJ SSR. AU - MALENCHENKO, A. (AN BEL0RUS5K0J ESR. MINSK. IKST. YADERNOJ EHNERGETiKtlc 0322500 OR - INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA (AUSTRIA >. 329*000 NU - IAEA-R—2659-F. PU - MAR 19B3. 26 P. NO - INCLUDES ENGLISH TRANSLATION. *E - ANTIMONY: ARSENIC; DIELECTRIC TRACK DETECTORS; HAIR; LEAD; MEN; MERCURY; NEUTRON ACTIVATION ANALYSIS;

22 I COM 1NUEOÏ RE - L141S: 83-783*82 OF RADON ANC THCRCN GASES *NC PARTICULAT E MATERIALS TI - COMPARATIVE ASSESSMENT OF RADIOLCGICAL IMPACT "aOM CONTAINING URANIUM AND THORIUM ANO THEIR DECAY PRODUCTS URANIUM AND THORIUM MILLING. FROM A REFERENCE URANIUM MILL AND A THCK 1UM MILL ARE AU - YUAN* Y.C.; ROBERTS* C.J. (ARGONNE NATIONAL LAB.* IL ( DESCRIBED. PCTËNTIAL RADIOLOGICAL IMPACT S RESULT ING FROM USA)!. 0**0000 OPERATION OF THE MILLS ARE SUMMAQ12ËD AN C COMPARED. OR - INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA «AUSTRIA); INDIVIDUAL EXPCSURE5 ARE EVALUATED PELAT 1VE TO THE LIMIT NUCLEAR ENERGY AGENCY, 7S - PARIS (FRANCE». 329*000; OF 25 MREM PEP YEAR IMPCSEO BY TM£ USEFA UPANIUM FUEL 4796200 CYCLE STANDARD. *0 CFR ISC. CALCULATIONS I NOICATE THAT NU - IAEA-SM 262/17.: ISBN 92-0-02028 2-9. THIS LIMIT MIGHT NCT eE MET » ITHIN AEOUT 3 KM OOtaNkIND DU - P« 505*519, MANAGEMENT CF WASTES FRCM URANIUM MINING AND FROM EITHER THE MCOEL U«*MU" CR THCHILM HILL. THE MILLING. PROCEEDINGS CF AN INTERNATIONAL SYMPOSIUM RESULTS OF THIS ASSESSMENT ALSC INDICATE THAT RADIATION JOINTLY ORGANIZED 6Y TH' IAEA AND THE OECO/NEA ANO HF.LD PROTECTION STANDARDS THAT LIMIT INC 1V1CU DCSES FRCM IN ALBUQUERQUE. 10-1* *-*Y 198 2. VIENNA. IAEA, 1982. 735 RADON AND THCRCN SHOULD eE ESTABLISHED. P. PROCEEDINGS SERIES. CC - INTERNATIONAL SYMPCSIL"" ON MANAGEMENT QF VASTES FROM URANIUM MINING AND MILLING* ALBUOUERQUE . f>M (USA). 10-1* A 92 •m.

26 (CCKT 1NUED) L 1 4 1 7 : flJ-779142 CATEGO RIES CF *CKK£BS F f. C " JCTl- CCCuPATIO *KC NON- BACKGROUND RAOIOACTIVITY IN THE MQNAZ1TE AREAS OF KFPALA. OCCUPA TION. RESULT5 OF THQKON VEASUWEMENTS FRQM TH£. I NO ï A . EXHALE BREATH CF PLANT »CRKERS AJ-E PRESENTED FHC** *HJCH SOMAM. S.D. THE BO DY BURDEN OF NATURAL THORIUM OEPCSITEO u LUKGS c*s KERNFORSCHUNGS ANLAGE JUELtCH G.M.Q.H. (GERMANY* F.R*). HE ESTIMATED* AN IMPCRTAsT PATHWAY OF E.XPCSUf>£, F Cfi IH KM ZENTRALABTEILUNG FUER CHEM1SCHE ANALYSE. 920Ï227 R N AHE HCST SUSCEPTIBLE. 15 NON-SPECIFIC INGESTICN JUËL-SPEZ—161 . CHILD SAND ITSELF. DATA C6TAINE0 C* ThE B*DCNuCt.IOE JUL J9fl2. 2ft P. QP RAW CF URINARY EXCBETICN CF CM1L0REK BELCNCING TC T»C BREATH; BUILDINGS; CALCIUM FLUOR IDES: CHILOREN; OOSE CONTEN OUPS AR£ DISCUSSED. (QRIG.I. RATES; EXPERIMENTAL CATA: INDU; INHALATICN; LUNGS: AGE GR MONAZ!TES; NATURAL RACICACTIVITY; PERSONNEL ; PERSONNEL DOSIMETRY; QUANTI TATIVE CHEMICAL ANALYSIS: RADIONUCLIDE KINET ICS; RAOON 220; RESPIRATION; SAND; THERMOLUMINESCENT DOSEMETERS: THORIUM ISCTCPRS; UPINE EXTERNAL RADIATION EXFCSURE MEASUREMENTS HERE CARRIED OUT •ITM NATURAL CAF? THEPHCLUKINESCENCË DOSIMETERS (TLOÏ IN ABOUT 2500 OWELLINGS AND ON ABOUT 10.000 PERSCNS LIVING IN MONAZITE AREAS OF «OLTH-VEST CCAST OF INC I A, STATISTICAL ANALYSIS CF THE DATA INDICATE THAT THE VALUES ARE DISTRIBUTED LCGNCRM ALL Y. A SYSTEMATIC STUDY WAS CARRIED OUT A MANAVALAKUR TCHI PLANT OF INDIAN RARE EARTHS LTD. AND ADJOINING HLO BACKGROUND AREAS TO OBTAIN TYPICAL AVERAGE RAOIATICN EXPOSURE TO DIFFERENT 000030

28 28 (COST INLJEO > L1*17: 83-778801 TOTAL DEAD. 3.0 FC£ ALL MALIGNANT TUMC^S. IQ.b FOft FOURTH FOLLOW-UP STUDY CN 272 THCROTRAST-ADM INISTEHED HEPATIC TUMORS* 10.2 FCK BLOCO DISEASES AND 6*4 FOR LIVER CASES* 1977 REPORT. CIRftMOSIS* IN THE 21 CASES »H) HA0 BEEN CIVES THCRCÎSAST (IN JAPANESE)• 6Y A ROUTE CTHEfl THAN [KTRAVASCULAH CNE» NC FATAL CASE MOR 1 • TAKESABUPn; KATC* YOSHIC (NATIONAL INST. OF RELATED TC THE THCRCïPAST ADMIN1STRATICN «AS OISCCVERED. RADIOLOGICAL SCIENCES* CHI BA (JAPAN)); MARUYAMA. TAKASHI i (AUTHOR 1 . OVA. YUKIKO* HATAKEY0WA, SHiGERU. 4 405000 ISSN 0048-0428. PU - NIPPON IGAKU HOSHASEN GAKKA1 ZASSHI. (SEP 1982)» V. 42(9) P. B49-908. KË BLDOO: CARCINOMAS; DELAYED PAOIATION EFFECTS; HEPATOMAS; LIVER; LIVER CIRRHOSIS; LUNGS; MEDICAL SURVEILLANCE; MORTALITY; OSTEOSARCCVAS; PATIENTS; RADIATION INJURIES; REFERENCE MAN; TH030TRAST THE FOURTH ED I OEM ICLCC!C4L FOLLCW-UP STUDY ON 272 THOROTRAST-AOM1NISTERTO KAR-WOUNOEO EXSCRVIC^MEN WAS CONDUCTED IN 1477, AFTER A LAPSE OF 32 TO 40 YEARS FROM THOROTRAST INJECTIONS* THE AUTHORS FOUNO TWENTY-F IVE MALIGNANT HEPATIC TUMORS* TWO LUNG CANCERS* ONE OSTEOSARCOMA ANO STXTEL'N OTHER MALIGNANT TUMORS WITH THREE BLOOD DISEASES ANO ELEVEN CASES OF LIVER CIRRHOSIS IN THE 2S1 CASES «HO HAP PEF.N GIVEN THCPOTPAST INTRAVASCULARLY. VALUES OF RELATIVE RISK WERE; L.E FOR 000030

41 L|«!«: 03-767808 IONIZING RADIATION; SCUaCES ANO eiOLCGlCAL EFFECTS. ( LRAO ABSTRACT.i ANON. NEW YORK, NY. UNITED NATIONS. 1962. 773 P. BACKGROUND RADIATION; BIOLOGICAL RADIATION EFFECTS; DAUGHTER PRODUCTS; DGSE LIMITS! DOSE-RESPONSE RELATIONSHIPS; GENETIC PADMMON EFFECTS: IONIZING RAD ! AT IONS: LIFE SPAN; MAN ; MATHEMATICAL MODELS; NATURAL RADIOACTIVITY; NUCLEAR EXPLCSIONS; NUCLEAR POWER PLANTS; OCCUPATIONAL SAFETY; RADIATION HAZARDS; RADON 220 ; RAOON 222; REVIËWS; RISK ANALYSIS: UNSCEAR SEPARATE ABSTRACTS »EPE PREPARED FOB THF. 1982 RËPOPT OF THE UNITED NATIONS SCIENTIFIC COMMITTEE ON THE EFFECTS OF ATOMIC RADIAT1CN TC ThE GENERAL ASSEMBLY AND FDR THE 12 SCIENTIFIC ANNEXES. «3 43 1CCNTINUtD) L1414 : 83-767762 FACTORS RELATING TC KAClu* UPT^i *NC PETEMICN RE CU I "E HUMAN HEALTH EFFECTS CF RADIUM; AN EP IDEM IOLOGIC STUDY, AS QO RISK FACTC^S MOOIFYING RISK CF 6CTM Tr-E PERSPECTIVE OF RESEARCH AT ARGONNE NATIONAL LABORATORY. CLASSICAL TUTORS, CStEOSAOCG^A AND KASA1, SINUS/MASTC1O» STnaniNCS* J-H. ANO THE MCRE «ECENTLV SUSPECT SQPT-TISEU6 TUCCKS. Iht ARGONNE NATIONAL LAB.. IL (USA). 0448000 HISTORY. ORGANIZATION. ANO ClBfiEM KESE*SCK ACTIVITIES lf\ ANL — «2-65-PT.2. EPIOEWICLCGY AT ACGCNNE KATÏCNAL L*eCRATCPlr ARE P. 1-20. RADIOLOGICAL AND ENVIRONMENTAL RESEARCH DESCRIBED. AKD F I KOI KGS CF THE LAST CECACE AKC A HALF OIVIS1ON. CENTER FOR HUMAN RAOICFLIOLOOV. ANNUAL REPORT, REVIE«EC« PLANS FCfi FUTURE ReSEASC^ Afi£ EfilEFLY JULY 1981-JUNE 1902. NOV 1982. DISCUSSED. AVAILABLE FROM NTIS. PC ALL/UF AO 1 AS 0E63007660. ANL; DELAYED RADIAT1CN EFFECTS; OIAL PAINTERS; OOSE- RESPONSE RELATIONSHIPS: EPICENICLCGY; HEALTH HAZARDS; LEUKEMIA; MAMMARY GLANDS; NEOPLASMS: RADIUM 226; RADIUM 228; RISK ANALYSIS: SKELETON THE TOPIC OF HEALTH EFFECTS OF RADIUM HAS RECENTLY BEEN CONSIDERABLY BROADENEC BY THE 10ENTIFICAT[ON CF MULTIPLE MYELOMA AS A SPECIFIC OUTCOME OF BONE-SEEKING RADIONUCLIDEST ANO PV EV10ENCE THAT THE INCIOENCE OF BREAST CANCER MAY BE SIGNIFICANTLY INCREASED BY RADIUM EXPOSURE. ALL SOFT-TISSUE TUMORS ARE NO» SUSPECT, ESPECIALLY LEUKEMIAS. CONCEPTS OF DCSE~RESPCNSE NEED TO HE BROADENED TO INCLUCE THE CONCEPT OF RISK FACTORS. OR• IF ONE PREFERS. OF SUSCEPTIBLE SUBGROUPS. BIOLOGICAL

45 tS (CONTINUED) RE LI413: 83-764429 USED IN THE CALCULATION* THIS IS EXEMPLIFIED IN DCSE Tl IS EXPOSURE TO POTENTIAL ALPHA ENERGY AN AOEOUATE INDEX CONVERSION FACTOR CALCULATIONS FC« OCCUPATIONAL EXPOSURE OF OOSE. (RADON ANO THORON DAUGHTERS.) TO RADON ANC THORCh OAUGHTERS AND CCMESTIC EXPOSURE TG JAMES. A.C. (NATIONAL RADIOLOGICAL PROTECTION BOARO. RADON DAUGHTERS. (U.K.I. HARWELL (UKII; JOHNSON. J.R. (ATOMIC ENERGY OF CANADA LTD.. CHALK RIVER» ONTARIO» CHALK RIVER NUCLEAR IA6S>>. •502700! 06*3000 NU ISSN 0308-4272. PU RAOIOL. PROT. BULL. (JAN 14831. (NO.50) P. 5-13. KE ALPHA OOSIMETRY; DAUGHTER PROOUCTS; OOSE LIMITS; INHALATION; MAN; MATHEMATICAL MGOELS: PARTICLE SIZE: RADIATION DOSES; RA01ATION PROTECTION: RADIOACTIVE AEROSOLS: RAOON 220; BACON 222 ICRP PUALICATION 32 RECOMMENOED LIMITS FOR INHALATIGN OF RAOON AND THORON DAUGHTERS BY WORKERS IN TERMS OF THE QUANTITY POTENTIAL ALPHA ENERGY. HOWEVER DOSIMETRIC «00ELLINO SHOWS THAT EXPOSURE TO POTENTIAL ALPHA ENERGY IS NOT UNIQUELY RELATEO TC DOSE. THE FACTOR CONVERTING INTAKE OF POTENTIAL ALPHA ENERGY TO EFFECTIVE OOSE EQUIVALENT DEPENDS PRINCIPALLY ON PHYSICAL AEROSOL CHARACTERISTICS, I.E. THE FRACTICN CF POTENTIAL ALPHA ENERGY NOT ATTACHED TC THE ATMOSPHERIC AEROSOL ANO THE AEROSOL SIZE 0I5TRIBUJIÇH; IT ALSO DEPENDS CN THE MOOEL

SO 50 ICGNT INUED ! RE - LI4II : 83-7SS28I MICHONUCLEUS APPEARANCE CCULC EE A^ INCICATCR OF Tl - MICRONUCLEUS IN A-BOMB SURVIVORS AND IN THCROTRAST RADIATION OAMAGE. ALSO THE M ICRC^CLELÎ APPEARANCE IN PATIENTS. ROUTINE EXAMINATIONS COULC SUGGEST THE PRESENCE OF (IN JAPANESE). CHROMOSOME ABERRATIONS. IN THE CASE OF TeCROTRAST AU - TANAKA. KIMIO: KAVAKAKI, MASAH1TC: IZUM1, TAKAKI; PATIENTS H-J BODIES APPEAREO IN HIGH RATE. (NAKAMSHI, SHIGETA» CHIHARU; TAKAHASHI* HIROSHII OHKITA. TAKESHI ( HIROSHIMA UNIV. (JAPAN). RESEARCH |NST. FOR NUCLEAR MEDICINE AND BIOLOGY,. 3000850 NU - ISSN 03*9-3228. PU - NAGASAKI IGAKKAI ZASSHI. (NOV 19801. V. 55 P. 762-766. KE - A-BOMB SURVIVORS', BLOOD FORMATION; 80NE MARROW CELLS; CHR0M0S0uAL ABERRATIONS; OELAYEO RADIATION EFFECTS: ERVTHROCYTES; HIROSHIMA; PATIENTS; REFERENCE MAN; THOROTRAST AB - MICRONUCLEUS ANO HOWELL-JOLLY (H-JI BODIES IN BONE MARHO» AND IN PERIPHERAL BLCCO WERE INVESTIGATED FOR 31 A-BOUB SURVIVORS. AND 21 THCROTRAST INJECTED PATIENTS •ITH 7 CONTROLS. THF RATE CF UICRCNJCLEUS IN MYELOERYTHHOBLAST "AS 0.2631 FOR A-BOMB SURVIVORS ANO 0.288» FOR THCROTRAST PATIENTS. WHICH WERE I-ICHER THAN THE CONTROLS. 0.0501. CORRELATIONS OF MlCRCNUCLEUS APPEARANCE WITH THE INCIOENCE OF CHHOMOSCBE ABERRATIONS ANO WITH FST|»ArgO EXPOSURE OOSE WERE CeSECVED, SUGGESTING THAT THE 000033 51 5^ < CCNT 1NUEO » CE - LI»OS: «2-745156 RAOCN UAUGMTE(-3 IS PROCEEDING. (G.t.l. Tl - B.AOON OAUGHTEHS IN HUMAN BEINGS* EXPERIMENTAL STUDIES OF THE OEPOSITÏON CP PAOCN DAUGHTERS IN THE EREATHING ORGANS OF HUMAN BEINGS. (IN S«EO1SH|, RAOCNOCETTRAR I MAENNISKAN. EXPERINENTELLA STUDIER AV HADONOOETTRARNAS UPPTAC I MAENN1SKANS ANONlNGSORGAN. OR - STATENS'STRAALSKYOOSINSTITLT. STOCKHOLM (SMEDENI. 5966500 NU - SSI-A—1)2-18. PU - * NOV I9H2. 23 P. KE - ADULTS: AIR; BUILDINGS: CHILDREN: INHALATION: MEASURING METHODS; MINES: RADIATION DETECTION: RADIATION OOSES; RADCN ISOTOPES •B - T»O DIFFERENT METHODS FCR THE MEASUBEXEKT OF AIRECRNE PAOON DAUGHTERS HAVE PEEN DEVELCPEO AND APPLIED TO VARIOUS ENVIRONMENTS. THE RELATIVE DEPOSITION OF RADON DAUGHTERS IN DWELLINGS IS FOUNO TO BE OF THE SAME SIZE AS IN MINES. «NO THE DEPOSITION IN CHILDREN TC BE AS LARGE AS IN ADULTS OR EVEN LARGER. THIS IS IN ACCORDANCE WITH THE THEORETICAL CALCULATIONS »HIO RESULT IK HIGHER DOSES TO CHILDREN THAN FCR GROWN UPS. THE VERIFICATION OF EXISTING MODELS OF DEPOSITION AND RETENTION OF INHALED

64 RE - L1406: 82-737554 Tl - ESTIMATION OF EFFECTIVE DOSE EQUIVALENT CF POPULATION. CAUSEO HV INHALATION CF RAOON. THORCN AND THEIR OECAV PRODUCTS. (IN HUNGARIAN). A RACCN-, TCHON-, VALAMIhT BOWLASTEHMEKEI INHALACIOJA OKOZTJI EFFEKTIV ECES2TEST OOZ1SEGYENEHTEK BECSLESE A LAKOSSAGRA. AU - TOTH. A. (8ARANYA MEGVEI KORHAZ-EENCELOEINTEZET. PECS ( HUNGARY)). 0733835 OR - EOETVOES LORANO FIZIK'I TARSULAT SUGARVEOELMI S2AKCS0P0RTJA. BUDAPEST (HUNGARY). 239*250 PU - P. 40. 'B2 TRAINING COURSE ON RAOIATICN PROTECTION HELD AT BALATONKCNESE• HUNGARY. 14-16 APR 1982. 1902. NO - PUBLISHED IN SUMMARY FORM ONLY. AVAILABLE FROM ELFT 5SZ. CO - '82 TRAINING COURSE CL RAOIATION PROTECTION, BALATONKENESE

69 69 (CCNTINUEOI RE - LI403: 82-724012 INCLUDED MEASUREMENTS CF ALPfA ANC BETA-CAHMA T| - FORMERLY UTILIZED MEO/AEC SITES REMEDIAL ACTION PROGRAM. CONTAMINATION, BOTH FIXED AN0 REMOVABLE; eETA-GAMMA RAOIOLOCICAL SURVEY OF UNIVERSAL CYCLOPES. INC.. EXPOSURE SEACINGS AT CCNTACT ANO AT 1 » I 3 FT) AECVE ThE TITU5V1LLE. PLANT (FCRH(RLV VULCAN CRUCIBLE STEEL FLOOR CP GRCLNC LEVEL; AND MEASUREMENTS CF THÇ COMPANY. ALIOUIPPA. PENNSYLVANIA, MAY 2-8. I97S). CONCENTRATIONS OF RACCN DAUGHTERS IN Alf: AND AU - «YNVEEN, R.A.; SMITH. «.H. Î «UNO (5. R.i.,; MAYES< CR- CONCENTRATIONS CF I37CS. THE 232TH OECAY CHAIN. THE 226RA OP - ARGONNE NATIONAL, LAB.. IL (USA). 044S000 OECAV CHAIN. ANO URANIUM IN THE SCIL CN THE SITE. NU - DOE/EV—000S/33.; ANL-OHS/HP—82-104. FOURTEEN SPOTS OF CONTAMINATION EXCEEDED ThE ALLChAtiLE OU - MAY 1982. 61 P. LIMITS FCR NATURAL URANIUM. UNOER CURRENT LSE CONDITIONS. NO - AVAILABLE FROM NTIS., PC A04/MF AOI AS 0E82016057. THE POTENTIAL FCR RAOIATICN EXPOSURE CF OCCUPANTS CF THE KE - ABANDONED SITES! ALOHA OETECTION; BETA 0ETECT10N; BU1LOING FROM THESE SOURCES CF CONTAMINATION IS REMOTE. BUILDINGS; CESIUM 137: DECOMMISSIONING; DECCNTAUINAT ION; CONCENTRAT ICNS CF HAOCN OAUGHTERS »EPE EELCh Tt-E 0-01 «L HUMAN POPULATIONS; NUCLEAR FACILITIES; PENNSYLVANIA; LIMIT. CALCLLATED RAOCN CONCENTRATIONS e'SEO CN TH£ RADIATION HAZARDS; RAOIATICN MONITORING; RADIOACTIVITY! RADON-DAUGHTER DETERMINATIONS SANGED FRCH 0-11 TO 0.27 RADIUM 226: PAOON; RISK ANALYSIS: SAFETY STANDARDS; PCI/L. THE CONCENTRATION GUlOE FCS 222CN IN UNCONTROLLED SOILS; SURFACE AIR; THORIUM 232; URANIUM AREAS IS 3 PCI/X. ANALYSIS OF SOIL SAMPLES FBC» THE SUE AB - A RA0I0L0G1CAL SURVEY «AS CONOUCTEO AT THE UNIVERSAL IN01CATE0 ELEVATED CONCENTRATIONS CF URANIUM (15.1 •- 0.7 CYCLOPS. INC. TITUSVILLE PLANT (FORMERLY VULCAN CRUCIBLE TO 109.0 *- 5.5 PCl/Gt n CNE SA»FL1NG LCCATICN NEAR THE STEEL COMPANY)• IN ALICU1PPA. PENNSYLVANIA, TO OETERMINE OUILDING. THERE CURRENTLY ARE NO EECLLAJCG» LIHIS FCR THE LOCATION AND QUANTITIES OF ANY RA0I0ACT1VE MATEPMLS URANIUM CONCENTRATION IN SCIL. BUT. A FKCPCSEO GUlOE REMAINING PN THÇ SITE AS A RESULT OF MED/AEC ACTIVITIES VALUE IS PCI/G. AFTEP EVALUATION CF RESULTS CF ThE IN THE LATE 1940S. THIS FACILITY «AS USED FCR ROLLING SURVEY. IT »AS CONCLUUEC TUT ALTHOUGH SCME AREAS Cf- THE URANIUM BILLETS DURING THE MED/AEC ERA. THE SURVEY 00003:) UNIVERSAL CYCLCFS FACILITY ABE C r»l AM I N A i F r. imt .tjc.c UJ X I 0,0 IUMJ/. • > O i - Z -«ID — • u!~ I UJU.H-JJJ (UV) _J uoaa uj — Q ill — ZJ _J Œ r I r > o anj zcwirt

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97 97 (CCNTINUEO) RE - L13I9: 62-69915» IT IS CGNCLUDEO THAT IT MUST OE BASEO ALMCS1 ENTIRELY Ch TI - FAILURES AND CP1TI0UE CF THE BEIR III LUNG CANCER RISK THE CZECHCSLCVAKI AN URANtu* MINERS. (AUTHCR). ESTIMATES. AU - COHEN. B.L. . V. «2(3) P* 267-26*. KF - COMPARATIVE EVALUATIONS; ENVIRONMENT; LUNGS. HAN: MORTALITY; NEOPLASMS; RADIATION HAZARCS; RADON AB - IT IS SHOWN THAT THE BEIR III PREDICTION OF LUNG CANCER INCIDENCE DUE TO ENVIRONMENTAL RADON IS MORE THAN TWICE THE ACTUAL INCIDENCE CF ALL LUNG CANCERS AMONG NON- SMOKERS, HISTOLOGICAL EVIDENCE FROM AUTOPSY STUOIES CF RADIATION VICTIMS AND CF HCN-SMCKERS IS REVIEWED. ANO IT IS SHOWN THAT NO MORE THAN 10X OF ALL LUNG CANCERS IN NON-SMOKERS CAN BE OUE TO RAOON. WHEN ALTERNATIVE CAUSES OF LUNG CANCER ARE CCNSIOEREO, IT IS CONCLUDEO THAT THE BEIR III ESTIMATES CF LUNG CANCER RISK DUE TO ENVIRONMENTAL RADON ARE TCO HIGH FOR NON-SMOKERS BY AT LEAST A FACTOR OF A6CUT «0. THE EVIDENCE FOR SYNERG1SM BETWEEN SMOKING ANO RADIATION INDUCED LUNG CANCER IS REVIEWED, ANO IT IS CONCLUDED THAT THE BE|H III ESTIMATES FOR SMOKERS ARE TOO HIGH BY AT LEAST A FACTOR OF AROUT 10. THE BASES FOR THE BEIR III XCOEL ARE REVIEWED. AND 000030

I0S 10a (CCNTINUE01 RE - LI316: 62-689072 LOWER LIMIT AND FCUFI HAO MCRÊ THAN 2QC PCI OF 224RA. THE TI - RADIOACTIVITY IN FCRMER WORKERS AT A THORIUM REFINERY. MEAN RATIO OF EMANATING 22«RA TO RETMNEC 212BI WAS 101 AU - RUNOO. J«; BREWSTER. C.R«; ESSLING. M.A.I SHAT J.Y. PCI/NCI WITH INOIVIOUAL VALUES RANGING FRO* 11 TO SB1. WRENN« M.E. (E0.>. THE PROBLEM CF INTERPRETING THE DATA IN TERMS CF THE PU - P. 261-267. ACTINIDES IN MAN ANO ANIMALS. LCS ALTCS. CA. ACTUAL AMOUNTS CF THOOHJM IN THE 1HOCA« IS 01SCUSSEO RD PRESS. 1981. BRIEFLY, KE - BISMUTH 212; CHEST: OAUGHTER PBCDUCTS; DELAYEO RAOIATION EFFECTS; EPIDEMIOLOGY: INDUSTRIAL MEDICINE: INHALATION; METABOLISM; ORE PROCESSING; PEBSCNNEL; RAOIATION DOSES: RAOIUM 224; THORIUM; THORIUM ORES AB - AS PART OF AN EPIDEMICLOGICAL STLOY OF THE POSSIBLE LATE O1OLOGICAL EFFECTS OF THORIUM, MEASUREMENTS HAVE REEN MAOE OF RADIOACTIVITY ATTRIBUTABLE TO THCRIUM OAUGHTERS IN ALMOST 200 MEN WHO HAD WORKED IN A THORIUM REFINERY WHICH CLOSED IN 1973. FCR EXTERNAL GAMMA-RAY MEASUREMENTS, STATISTICALLY SIGNIFICANT RESULTS T> 2 SIGMA) WERE OBTAINEO IN SS OF THESE. WITH THREE SHOWING MORE THAN 2 NCI 21261 TN THE THORAX* FOR MEASUREMENTS OF DAUGHTERS OF EXHALED THCRON. STATISTICALLY SIGNIFICANT RESULTS WERE OBTAINEC IN ALMOST EVERY CASE. RUT FOR 63 SUBJECTS THÇ VALUES CF <2 PCI CF FREELY EMANATING ?»*BA AT THE MOUTH COULD NCT 6E ATTRIBUTED UNEQUIVOCALLY TO TMCHIUM ACQUIRED OCCUPAT ION ALLY ; 131 MEN EXCEEDEO THIS 00003) 1 09 L 1 3 1")! fl2-6B69*t MEASUREMENTS OF THE THORIUM, URANIUM AND POTASSIUM CONCENTRATION IN SC»E SAMPLES OF THE ASHES FBCM POLISH POwER-STATIONS. (IN POLISH). PCMIACY KONCENTRACJ1 TCPU» UPANU I POTASU « WYHRANYCH PROBKACH PCPICLOW w ELEKTRCWNl W POLSCE. ZASTAWNY. A.; KVASNIEWICZ. E.i RABSZTYN. U. (POL 1TECHNIKA SLASKA. GLIWICE (PCLANDI. INST. FIZYKII. S25B880 ZESZ. NAUK. POLITECH. SLASK., MAT.-FIZ. (19801. (SO.321 P. 43-51. ASHES; BUILDING MATERIALS: CALIERATION STANDAROS: OOSE RATES: FOSSIL-FUEL PC»EH PLANTS: GAMMA SPECTROMETERS: GONAOS: HUMAN POPULATIONS; POTASSIUM 40: BAOIATION HAZARDS: SC1NT1LLATICN COUNTERS; THORIUM; URANIUM 238 • THORIUM, URANIUM AND POTASSIUM CONCENTRATION WERE MEASURED IN 19 SAMPLES EY MEANS CF THE SAME GAMMA SPECTROMETER, PARTICULAR ATTENTICN HAS PA10 TO THE PREPARATION OF THE STANCARCS. THE RESULTS OF THE MEASUREO CONCENTRATION AR? CLCSEC IN THE RANGES (5-64). 10-6 G/G FOR THORIUM. , 10-6 G/G FCP URANIUM AND (2-311, 10- 3 G/G FOP POTASSIUM. (AUTHOR).

1 10 110 (CONTINUED) RE - L131S: 62-68689» BISK/TONNE IN tERMS CF FATAL CANCER OCSES. IF INGESTEd. TI - EFFECTS OF 1CRP PUBLICATION 30 AND THE 1980 BEIB REPORT PER TONNE CF URANIUM, »HEN THE RESULTING CURVES ARE ON HAZARO ASSESSMENTS CF HIGH-LEVEL WASTE. COMPAREO WITH thCSE CALCULATED PBEVICUSLY (BASED CN ICt-P AU - COHEN. O.L. (PITTSBURGH UNIV.. PA (USAII. 5223000 PUBLICATION 2 ANO THE K72 BE1S CEPCRT). THE HAZARC IS NU - ISSN 0017-9078. LESS FOR THE FIRST CENTURY BLT MUCH MCRE THEREAFTER. THE on - HEALTH PHYS- (FEB 1982). V. «2(21 P. 133-1*3. PRINCIPAL SCURCES CF THIS GREATLY INCtEASEO HAZARO IS THE KE - ACTINIUM 227; AMERICIUM 24 1: AMERICIUM 243: CESIUM 13S: 100-FOLC INCREASE IN ABSGRPTION THROUGH THE GUT Foc 237NP CESIUM 137; CURIUM 244; HIGH-LEVEL HAOIOACTIVE HASTES: IN ICRP 30. PLUS THE HIGH CANCER RISK FCCM RAD1ATICN TC ICRP: IODINE 129: LEAC 210; MAN; NEOPLASMS; NEPTUNIUM 23T; ORGANS; PLUTONIUM 239: PLUTONIUM 2*0: PROTACTINIUM ANO SOME SCIENTIFIC ÔuESTICNÎ RELEVANT TC ASCERTAINING 231; P«R TYPE REACTORS: RADIATION HAZAHOS; RADIUM 225; THEIR VALIDITY ARE DISCUSSED. (AUTfCRI. RADIUM 226; RISK ANALYSIS* STRONTIUM 90: TECHNETIUM 99; THORIUM 229: THORIUM 230; THORIUM 232; URANIUM 233: URANIUM 234; URANIUM 235; URANIUM 236: URANIUM 230; ZIRCONIUM 93 AH - ICRP PUBLICATION 30 (ICRP30) GIVES THE RAO1ATION DOSE TC VARIOUS BODY ORGANS IN SV PER BOI WHICH ARE READILY TRANSLATED INTO RAD FER CURIE INGESTED FOR VARIOUS RAOIOISOTOPES: THE 1980 BEIR REPORT (BE IR 111) GIVES THE PISK OF FATAL CANCER CEP RAO CF DCSE TO EACH BOOV ORGAN; THE ORIGEN 2 COOE GIVES THE CURIES PER TONNE OF INITIAL URANIUM FUEL IN HIGH LEVEL WASTE AND IN SPENT FUEL. THE PROOUCT OF THESE, CI/TCNNE X RAO/CI X BISK/RAD GIVES THE

1 1 B 118 (CCNTINUEO) RE - LI309: 82-668671 PROXIMITY TO URANIUM KILL TAILINGS AFFECTEC Trf LEVtLS OF Ti - THORIUM CONTENT OF HUMAN TISSUES. 230TH IN TISSUES. AU ~ IBRAHIM, S.A. (NEW YCRK UNIV., TbXEOC); SINGH* N.P.i COHEN, N,; SACCOMANNC, d.i WRENN. M.E. WRENN. ».E. (EO.I. PU - "• 207-216. ACTINIOES IN MAN AND ANINALS. SALT LAKE CITY. UT. RO PRESS. I9S1. CO - WORKSHOP ON MEASUREMENT ANO INTERPRETATION OF ACTLNLOE ACCUMULATION BY MAN. SNCW9IRD, UTT USA« 14 - 18 OCT 1979. KF - ALPHA SPECTRPSCOPY; AUTCPSY; OISTRIBUTICN; GEOGRAPHICAL VARIATIONS; INHALATICN; KIDNEYS: LIVER: LUNGS: LYMPH NOOES; MAN; HAOIOMETCIC ANALYSIS; RADICNUCLIDE KINETICS: SKELETON; THORIUM ISCTOPES; THORIUM 22a; THORIUM 230; THORIUM 232: TISSUES AB - ALTHOUGH THE ELEMENT THCRIUM IS WIDELY DISTRIBUTED IN THE ENVIRONMENT, THE AMCLNT ANC DISTRIBUTION IN THE HUMAN HOOY HAS NOT BEEN AS THOROUGHLY STU01E0 AS THE CTHER NATURAL GA010NUCLIDES, SUCH AS RADIUM. BECAUSE IT HAS SIMILAR CHEMICAL ANO G ADI 08IOL0G ICAL PROPERTIES TO PLUTONIUM, THE AMCUNT AND DISTRIBUTION OF THE MAJCR ALOHA-EMITTING ISOTOPES CR THCRIUM (I.E., 232T*. 2J0TH, ANO ?28TH) WERE DETCRMNED IN THE IVPCATAKT ORGANS OF THE HUMAN noPY. FURTHCRWCRE« IT WAS DETERMINED «HETHFR I 19 119 (CCNTINUEOI RE - L1309: 8Z-66B6e5 THE INDUCTION CF OSTECGEMC SARCOMAS. ihC&IUM-zge hAS A TL - TOXICOLOGY OF 22BTH IN YOUNG »DULT BEAGLES! POTENTIAL NUMBER OF SHOBT-LIVEO CECAV PRCOUCTS fchlCH LEAVE ThE RELATIONSHIP TO THE THORIUM FUEL CYCLE. SUES DF FORMATION. »N0 BECI STB I Bui ICN IN ACCCRO »ITf AU - STOVER* B.J. FUNIV. OF NORTH CAROLINA* CHAPEL HILL). THEIB SPECIFIC NUCLEAR ANO EXTRANUCLEAC PROPERTIES. THE VRENN, M.E. CEO.}. VARIATION RESULTS FRCW THESE PROPERTIES CF THE SEVERAL PU - P. 483-492. ACTINIOES IK MAN ANO ANIMALS. SALT LAKE CITY. DECAY PHCOUCTS. FROM THE EFFECT CF UCKE-SE MODEL I KG Ck THE UT. RD PRESS. 1981. MICROOISTHIBUTION OF 22eTH. ANO FECM CAU1ATICN DAMAGE TO CO - WORKSHOP ON MEASUREMENT *NC INTERPRETATION OF ACTINIOE THE SKELETON. THESE FACTCBS COMBINE TC MAKE THE SKELETAL ACCUMULATION BY MAN. SNGMBIRD. UT• USA. 14 - 18 OCT 1979. MICRODOSIMETBY CF 228TH 1NTRIGUINGLY COMPLEX. KE - BEAGLES: BLOOD PLASMA: DAUGHTER PROOUCTS; DELAYED RADIATION EFFECTS: CISTBI BUT ION : MICRCOOS IMETHY; OSTEOSARCOMAS: RAO1ONOCLIDE KINETICS: SKELETON: THORIUM 228: TISSUES AB - THORIUM-228 HAS ORIGINALLY INCLUDED IN THE EXTENSIVE PROGRAM AT THE UNIVERSITY OF UTAH TC INVESTIGATE THE EFFECTS OF 239PU ANO CTHER RADIOACTIVE MATERIALS. THE SOLUTION CHEMISTRY ANO* HENCE* THE DISTRIBUTION ANO RETENTION IN BIOLOGICAL SYSTEMS OF TETRAVALENT TH IS SIMILAR TO. BUT NOT IOENTICAL KITH, THAT OF TETRAVALENT PU. HOWEVER. THE NUCLEAR PROPERTIES ANO. HENCE. THE M1CRODOSIMETRY IN BIOLOGICAL SYSTEMS. OF 228TH AND 239PU DIFFER VASTLY. THE PRINCIPAL SITE OF DEPOSITION OF 228TH IS ON THE SURFACES OF BONE. AND THE PRINCIPAL EFFECT IS

133 133 fCONTlNUED) RE - L1224! 81-641279 BEEN TRIED TO COMPILE THE DISTRIBUTION CF THE LYMPH NODES Tl - BIOPHYSICAL INVESTIGATIONS OF THE DCSE-EFFECT IN THE DIFFERENT REGIChS CF THE BODY. ANNUAL OCSES HAVE RELATIONSHIP IN CHROMOSOME ABERRATIONS OF HUMAN BEEN CALCULATED IN THESE DIFFERENT REGIONS IN CROEB TO LYMPHOCYTES CAUSED BY THOROTRAST DEPOSITS. PT. 2. FIND A REPRESENTATIVE VALUE FOR THE «HCLE EOOY. THE BIOLOGICAL ANO MEDICAL ASPECTS. VALUES DESCRIBING THE KINETICS OF THE LYMPHOCYTES IN THE AU - STEINSTRAESSER. A.; KEMMER, «.

134 134 (CONTINUED) BE - LI224: 81-64I27S ANALYSING SYSTEM.1 (TASI IS DESCRIBED. S I JE-0 I STH IBUT IONS Tl - BIOPHYSICAL INVESTIGATIONS OF THE DOSE-EFFECT OF THOROTRAST CONGLOMERATES CF LYMPH NCDES FRO" THE NECK. RELATIONSHIP IN CHROMOSOME ABERRATIONS OF HUMAN THE LUNG AND FRCM THE LOaEB AORTA (BIFbRCATIC) ARE GIVEN. LYMPHOCYTES CAUSEO BY THOROTRAST DEPOSITS. PT. I. IN THE LYMPHATIC SYSTEM MOPE THAN 90X CF ThE AESORBED PHYSICAL ASPECTS. DOSE IN TISSUE IS DUE TC ALPHA-PABTICLES. THE COMPUTATION AU - STEINSTRACSSEfl. A. (UN IVERS IT ACT OES SAARLANOES. HCBURS/ METHOO CF CALCULATING Tf-E SELF-ABSCRPTICN CF ALPHA- SAAR 'GERMANY. F.R.). INST. FUER BIOPHYSIK). 6508700 PARTICLES IN THE CCNGLCMERATES ANO OF CALCULATING THE NU - ISSN 0J01-434X. ANNUAL OOSES IN THE LYMPH NODES IS OESCBIBEO. THE VALUES PU - RADIAT. ENVIRON. BIOPHYS. (FEB 19811. V. 1911) P. 1-15. LIE BETaEEN 135 ANO 1200 RAO/YEAR. THE CCNTR1BUT10N TO IRRA0IAT10N FHCM GITSIDE THE LYMPHATIC SYSTEM CAN EE KE - AUTOPSY; BIOLOGICAL CCSEMETEHS; eioPHvsics: CALCULI: NEGLECTEO. THE METHOD CF DOSE OETERMINAl1CN IS DISCUSSED CHROMOSOMAL ABERRATIONS; OCSE-RESPONSE RELATIONSHIPS; AND COMPARED t I TH MICRCOCS1METEI C METI-CCS. IITh THESE ENERGY TRANSFER; LVMFh NODES; LYMPHOCYTES; PATIENTS; METHODS. THE OC£E OF A LYMPHOCYTE CAuSEC GV CNE HIT CF AN RAOIATION OOSES: RADIATION INJURIES: STATISTICS; ALPHA-PARTICLE LIES BETaEEN eo AND 920 RAC. ENERGY THOROTHAST DISSIPATION DOES NCT TAKE PLACE »NC THE TCTAL ENERGY AB - THE PAPER DESCRIBES THE PHYSICAL ASPECTS CF OOSE ERMITTEO ACTS ON THE LYMPHOCYTES ïr-US INCLCIKG CHRCMGSCME EVALUATION. THE CHRCMOSCME ABERRATION RATES OF THOROTRAST ABERRATIONS. - UUJN OO W1— UI a acr- < JOXJIV —« XUJU, O X a D IU.H U.OUJU I 4 U. 33 O 3 < u*u •- X~ 4 ex t- u UjZ»- 4«-U U 4 >l?U ,_ 4 U !_ Z UJ 3 *»- O U4 UJ oixi/i a) a U 4 OJ Z UJ 4 Q *~ x a a a — UJ 5zo UJ »-QUJZtUZ>JO 4 X >-Ul/lQ. Z a u — 3.JZ O 4 »- Z Ullihh J»4 4 QU * -j <_i ZI/ICEma x 34 ? - o OIJOUJ) »-UJ û. x -" « U > U «J XLJ

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170 170 (CONTINUED) RE - L121A: S1-61S53S TEST PERSONS IN SALZeuRC. AUSTRIA. EACI- PESSCN «AS Tl - DISTRIBUTION PATTERN CF RA00N ANO OAUGHTERS IN AN URBAN QUESTIONED REGARDING HIS LIVING ACTIVITY. I.E.. 11-1 MEAN ENVIRONMENT AND DETERMINATION OF CRGAh-OOSE FREQUENCY TIMES HE SPENT IN INDIVIDUAL SLEEPING. LIVING. ANO DISTRIBUTIONS. WORKING PLACES ANO THE CCRRESPCND1NG PHYSICAL ACTIVITIES AU - STEINHAEUSLERi F. (UMV. CF SALZBURG. AUSTRIA): HOFMANN. THAT STRONGLY INFLUENCE THE RESP1RATCRV "INUTE VOLUME ANC ».; POHL. E.I POMC-BUELING. J. CONSEQUENTLY THE INHAwEO RADIOACTIVITY. AT ALL THESE GESELL. T.F.; LOwDER. k.M. (EOS.). PLACES. THE ANNUAL MEANS CF THE EXTERNAL GAMMA RAOIATfGM OR - DEPARTMENT OF ENERGY I CAK RIOGE. TN (USA). TECHNICAL AS WELL AS OF THE AIR CONTENT CF 222RN ANC ITS SHORT- INFORMATION CENTER. «05437 LIVED DECAY PRODUCTS WERE DETERMINED. FRCM AIL THESE NU - CCNF-7<0.>2Z-~< VOL.2). MEASUREMENTS < MORE THAN (1000) AND THE INFORMATION PU - P. 1145-1162. NATURAL ITADIATTON ENVIRONMENT III. 1980. OBTAINED. MEAN ANNUAL CRGAN DOSES WERE CALCULATED FOR CO - CONFERENCE ON NATURAL RADIATION ENVIRONMENT III. HOUSTON, EACH TEST PERSON. THE OOSES DUE TO COSMIC RADIATION, 4 OK. TX. USA. 23 - 28 APR 1>J78. ANO OTHER RAOIONUCLIOES INCORPORATED WERE TOTALED. THE KE - AUSTRIA; BLOOD; BONE HAHRC»; COSMIC RADIATION; DAUGHTER RANGE OF THE MEAN ANNUAL OOSES IN M1LLIKEVS IS CNLY FROM PRODUCTS; DRINKING WATER: GAMMA RADIATION; GONAOS: HUMAN 73 TO 126 FCH GCNAOS ANC 73 TO 336 FCR THE KIDNEYS ANO POPULATIONS; KIDNEYS; LEAD 210; LEAD 212; LIVER: FINALLY REACHES FRCN 117 TO 10.700 FOR THE BASAL CELLS OF POTASSIUM 40; RADIAT ICN DOSE 01STHI8UTIONS : THE BRONCHIAL EPITHELIUM. RADIOACTIVITY; RADIUM 226: RADON 220; RADON 222; RESPIRATORY TRACT CELLS: SKELETON; UREAN AREAS AB - IN A NORMAL URBAN ENVIRONMENT. INHALED RADON AND ITS DECAY PRODUCTS CAUSE AN IMPORTANT PART OF THE HUMAN RADIATION BURDEN NOT CK'LY FOR THE RESPIRATORY TRACT BUT ALSO FOR SEVERAL OTHEP CRGANS. A STUDY WAS MADE WITH 72?

1 78 178 (CCNTINUEDI RE - LI209! 8t-600456 AT THIS TIME. HOWEVER. DUE TC OlFFEfltNCES IN SOME Tl - ENVIRONMENTAL IMPACT CF RADIOACTIVE RELEASES FROM RECYr'E ASSUMPTIONS UT1LWE0 BY THE VARIOUS INVESTIGATORS ANO THE OF TH0RIUM-8ASE0 FUEL USING CURRENT CONTAINMENT LACK IN SOME CASES OF SITE-SPECIFIC METECCCLCGY ANC TECHNOLOGY. POPULATION OATA AV THORIUM RESOURCE SITES IN THE WESTERN AU - TENNERV, V.J.; BOMAR, E.S.: BCND. W.O.; MORSE, L.E.; UNITED STATES. A 0IST1NCT DIFFERENCE RESULTING FRO» THE MEYER. H.R.: TILL. J.E.; VALCINTAS. M.G. (OAK RIOGE SHORT HALF-LIFE OF 220RN (T/SUB 1/2/ = 56.C SI IN THE NATIONAL LAB.. TNt. THORIUM OECAV CHAIN COPACEO TC THAT fCS 222RN (T/SUO 1/ OR • ARGONNE NATIONAL LAB.. IL (USA). 0448000 2/ * 3.82 0) IN URANIUM OECAY WAS NCTEO FCR EMISSIONS NU - CCNF-800334 (VOL.2). FOLLOWING MILL SHUTDOWN. THIS EFFECT IS TO MAKE POTENTIAL PU - P. 1-IS. PROCEEDINGS OF THE SECOND OS DEPARTMENT OF RELEASES FCLLCAING THORIUM MILL SHUTDOWN CF LESSER ENERGY ENVIRONMENTAL CONTRCL SYMPOSIUM. VOLUME 2. CONSEQUENCE THAN IN THE URANIUM CASE. THCRIUC TAILINGS NUCLEAR ENERGY. CONSERVATION. AND SCLAR ENERGY. JUN 1980. ACTIVITY WOULD ALSC OECF.EASE RELATIVELY CAPIOLY DUE TO CO - 2. OOE ENVIRONMENTAL CONTROL SYMPOSIUM. RESTON. VA. USA. THE COMPARATIVELY SHCRT HALF-LIFE (T/SOE 1/2 * 5.7Ï Y) CF 17-19 MAR 1980. 22BRA. OOSES DUE TC AIRBORNE RELEASES FRCM THORIUM- «E - CARBON 14: CESIUM 131; COMPARATIVE EVALUATIONS: DECAY; URANIUM CARRIOE FUEL REFABRICATICN ARE SIGNIFICANTLY LESS DOSE COMMITMENTS: ENVIRONMENTAL IMPACTS; FEED MATERIALS THAN THAT DUE TO FUEL REPROCESSING, TRITIUM IS THE PLANTS; HUMAN POPULATIONS; MF. TECBCLCGY; MINING; ORE PRINCIPAL CCNTRIBUTCR TC REPROCESSING PLANT COSES »HILE PROCESSING; RADIATION OOSES; RADIOACTIVE WASTES; RAOIUM CARSON-14. 13ICS, ANO 232U ACCCUM FCH MCST CF THE 228; RAOCK 2?O: RAOON 222; THORIUM; THCRIUM CYCLE; REMAINING DOSE. A TENFOLD INCREASE IN T£PBCCCS S ING PLANT TRITIUM; URANIUM ORES; URANIUM 232 CF FOR TRITIUM RECUCES PCTH 1NCIVICUAL ANO PCPULAT1CN ART - THE ANALYSIS OF THORIUM MINING AND MILLING SUGGESTS THAT ÛOSES OV ABCLT 60X. FCfi PEF AEk\cAT ICN CFEKATICNb. à NEAh THE RESULTING OOSES SHCULO BE SIMILAR TO THOSE FROM LI NE AH OfcPfc'NOENCE LPCN OCSE .[TM 222L CCNTENT CF THE FUEL URANIUM PPEO*TIONS. *N APSCLUTE COMPARISON CANNOT RE "A3E 000030 • AS CALCULATED FtETwECN tCNCF. NT K A T | CNS CF 10 FP* ANC 500Û 104 (CONTINUED) i « URANIUM-2J2 IS AN IMPORTANT BY-PHCCUCT IN THE THORIUM L1208: ftl-595630 FUEL CYCLE BECAUSE CF IIS HIGH ACTIVITY IN PEPF.GCESSEO SIMULATION OF THE RETENTION AND DOSIMETRY OF Z32U AND ITS t-UEL. THE 232U DECAY CHI^ MAY PRESENT A LN1CUE DAUGHTERS AFTER INHALATION IN THC2 CR UO2 PARTICLES, INHALATICN HA7AR0 BECAUSE CF THE SHCHT HALF-LIVES Cf THE GRIFFITH. H.C.; CUOOIHV. R*G.; HCOVER, M.D.: STALNAKER. DAUGHTER RADIONUCLIDES AND THE Six ALPHA-PARTICLE N.D. «LOVELACE BIOMEDICAL AND ENVIRONMENTAL RESEARCH EMITTERS IN THE CHAIN. IN THIS STUCY. PCS51QLE AND THE INST., ALBOOOEOQUE. K>L. SIX ALPHA-PARTILCE EMITTERS IN THE CHAIN. IN THIS STUOY, SAN-OEPS. C.L.; CROSS, F.T.; OAGLE* G.E.; MAHAFFEY. J.A. ^ POSSIBLE RADIONUCLIDE RETENTION PATTERNS «ERE SIMULATED EOS.I. TO ESTIMATE THE OCSES RfcCEIVEO HY INTERNAL DCDY ORGANS OH HUMANS EXPOSEO TO SPHERICAL UC2 ANC THC2 PARTICLES DEPARTMENT OF ENERGY, WASHINGTON. DC (USA). OFFICE OF CONTAINING 222U. LLNG CLEARANCE OF THE SAD1CNUCLIDE S US HEALTH AND ENVIRONMENTAL RESEARCH: ËATTELLE PACIFIC PROJECTED AS BEING COMPCSEO CF COMPETITIVE PROCESSES. NORTHaEST LIBS., RICHLAKO, «A (USAI. 950S292: 9500022 1NCLUOING MECHANICAL CLEARANCE OF FARTICIES TC THE CONF-791002—• GASTROINTESTINAL TRACT» DISSOLUTION OF PARTICLES* RECOIL CO P. 193-206. PULMCNAPY TCXICOLOGY CF RESPIRABLE PARTICLES. EMANATION CF DAUGHTER PSCCUCTS PRCCUCEC EY ALPHA-PARTICLE SEP 1980. DECAY, AND O1FFUSICN EMANATION OF 220RN FRCM PARTICLES. IN THE MODEL IT «AS ASSUMED THAT PAD1CNLCLIOES OF THE «E 19. ANNUAL HANFORO LIFE SCIENCES SYMPOSIUM. RICHLAND* HI, 232U DECAY CHAIN DISSOLVING FSCM CR RECOILIG CUT OF THE USA. 22 - 2« OCT 1979. PARTICLES «ERE ABSORBED INTO THE SYSTEfrIC CIKCUIATICN AND AEROSOLS; BIOLOGICAL HALF-LIFE: BIOLOGICAL RAOIATICN TRANSLOCATED TO OTHER ORGANS OR EXCRETEO. THE SIMULATED EFFECTS; DAUGHTER PRCDUCTS: DOSE-RESPONSE RELATIONSHIPS; RETENTION PATTERNS CF THE RA01CNUCLI CE S IN AN CRGAN aERE DOSIMETRY; GASTROINTESTINAL TRACT; HEALTH HAZAROS; USEO TO ESTIMATE DC5E CCMM1TMEKT TC THE CRGAN. RESULTS Of INHALATION; LUNG CLEARANCE: LUNGS; MAN; MATHEMATICAL » SENSITIVITY ANALYSIS SHCaEC THAT THE CPGANS RECEIVING MODELS: PARTICLES: RAOICNUCLIOE KINETICS; RAOIOSENSITIVI TV; RADCN 220: RETENTION: THORIUM OXIDES: TOXI192 C ITY; URANIUM OXIDES; URANIUM 232 192 (CCNT1NUEO1 RE - LI205! 00-584767 IN CONNECTION «ITH EXPERIMENTAL INVESTIGATIONS. IT IS TI - INFLUENCE OF VENTILATION. EXHALATION AND DEPOSITION USEFUL TO STUOY THEORETICALLY THE »AY IN »HICH AIR PROCESSES UPON THE CONCENTRATIONS OF RN ANO TN ANO THEIR CONCENTRATIONS INOOCRS DEPEND CN RN- AND TN-EXHALATI ON DECAY PROOUCTS IN ROCM AIR. FROM THE «ALL. A I « EXCHANGE. OuTCCCC CCNCEMfAT IONS. AU - PORSTENOOERFER, J.i SCHRAUB. A.; WICKE. A.; SCHE1BEL. A. AEROSOL CONDITIONS AND DEPOSITION PROCESSES. THIS STUDY (INSTITUT FUER BIOPHVS1K, G1ESSEN. GERMANY). HAS BEEN CCNE CN THE BASIS OF A SIMPLE SCO* MGCEL CY ANON. VARIATION OF THE PARAMETERS ABCVE AND ev CCNSICERING PU - P. 530-537. TENTH MIDYEAR TOPICAL SYMPOSIUM OF THE KNOWN EXPERIMENTAL OAT». NORTHEASTERN NEW YORK CHAPTER* HEALTH PHYSICS SOCIETY- ON NATURAL RADIOACTIVITY IN MAN'S ENVIRONMENT. TROY, NY. RCNSSELAER POLYTECHNIC INSTITUTE. 1976. CO - 10. MIDYEAR SYMPOSIUM FOR HEALTH PHYSICS SOCIETY. SARATOGA SPRINGS, NY, USA. II - 13 CCT 1976. IE - AIR CLEANING; BUILDINGS: COMPARATIVE EVALUATIONS; DAUGHTER PRODUCTS; OECONTAMINATI ON ; DEPOSITION; EKHALATTON; FLCA MCOELS: NATURAL RADIOACTIVITY: RADIATION MONITORING; RADON; RACON 220: VENTILATION »B - THE NATURAL EXPOSURE COSE OF MAN IN HOUSES IS CAUSED PRIMARILY BY THE GAMMA-RADIATION CF AOK ANO OF NUCLIOES OF THE URANIUM-RADIUM ANO THORIUM SERIES, WHICH ARE MORE OR LESS IN ALL BUILDING MATERIALS. IN ADDITION TO THE EXTERNAL DOSE, THE INTERNAL RAOIATICN OOSE BY INHALATION OF RN ANO TN AND THEIR DECAY PRODUCTS IS NOT NEGLIGIBLE*

20a 208 (CCNT1NUED) «E LI120: no-ss*a«A RADIOACTIVE PARTICLES; THE FRACTION CF UNATTACHED TI OOSE TO TISSUES ANO EFFECTIVE DOSE EQUIVALENT BY DAUGHTERS ATOMS; THE VELOCITY CF CILIAtY TRANSPCRTi THE INHALATION OF RADON-222, RADON—220 ANO THEIR SHORT-LIVED DESORPT10N RATE OF ATTACHEO OAUGHTER ATOMS FROM THEIR OAuGHTERS. PARTICLES; THE ABSCRPTICN RATE TC 6LCCC; ANO THE OEPTH OF JACOB!, ».: EISFELD* K. THE BASAL CELL LAYER IN THE BRONCHIAL CENERATICNS. A GESELLSCHAFT FUER STRAHLEN- UNO UMWELTFOflSCHUNG M.B.H. COMPUTES PROGRAMME IAS SET-UP FOR THE CALCULATION CF THE MUENCHEN, NEUHESBEBG IGEBMANY, F.R.). INST. FUEB ACTIVITY AND DCSE O] STfl J f»V7l CH IV 7Hf LU^GS *S FUNCTION STRAHLENSCHUTZ. 2790200 OF THESE PARAMETERS. FCR THE EVALUATICN CF THE EFFECTIVE NU GSF-S 626. OOSE FROM INHALED MIXTURES OF P.N-222- ANO RN-220- PU FEB 1980. 131 P. OAUGHTEBS THREE OIFFERENI ALTERNATIVES FCR THE aEICHTlNG KE BLOOD, BRONCHI; DAUGHTER PROOUCTS; GASTROINTESTINAL OF THE MEAN DOSES TO THE TARGET TISSUES IN THE LUNGS ABE TRACT; INHALATION; LCCAL RADIATION EFFECTS: MAN: DESCRIBED. TAKING INTO REGARC POSSIBLE CIFFERENCES PERSONNEL: RADIATICN COSES; RADICNUCLIDE KINETICS: BETWEEN THE CANCEROGENIC SENSITIVITY CF THE TARGET CELLS RAOIOSENSITIVITY: RADCN 220; RAOCN 222; DETENTION; SAFETY IN THE BRONCHIAL AND ALVEOLAR REGION. CN THE BASIS CF 1HE STANDARDS; STATISTICS: TRANSLOCATION RESULTS CF THIS SENSITIVITY ANALYSIS MEAN VALUES FCR THE IN THIS STUOY THE RESULTS CF A SENSITIVITY ANALYSIS ARE EFFECTIVE DOSE To ADULTS PER UMT CF INHALED PCTENTIAL DESCRIBED «H1CH SHO«S THE INFLUENCE OF RELEVANT PHYSICAL ALPHA-ENERGY I IN JOULE» AND PER UNIT CF PCTENT LPHA- •ND HIOLOGICAL PARAMETERS CN THE OOSE FROM INHALEO RN- ENERGY (IN kLM) OF OAJGHTERS MIXTURES ARE CEPIVEO S 227. RM-2 20 ANO THEIR DAUGHTERS TC THE HASAL C!LL LAYER FUNCTION OF THE UNATTACHED FRACTION CF PCTENTIAL * PHA- C1F THE BRONCHI. TO THF PULMONARY TISSUES AND TO OTHCR ENERGY IN AIR AND THE CESOSPTICN HALF-L1HE TIME CF "OOY TISSUES. THF USEC «COÇLS FCR DEPCSITICN, RETENTION ATTACHED DAUGHTER ATC**S IN THE LUNGS. IN ACC1TICN AND OOSIMETRY CF INHALED OAUGHTEUS TAKE INTC REGARD TI F. EFFECTIVE DOSE FRCfc» INHALEC RN-22? AND CN-22C (» P -2 1b) VARIATION OF FPLLFIWINC PARAMETERS! THE AMAO OF INHALFO IS EST1MATE0 ANO CC»P»CEC MTH THE EFFEC1IVE OCSE UCM 20fl (CONTINUED! 201 INHALED DAUGHTERS. FINALLY THE CCN5EC1UENCES FCB THE RE - Li 120: eo-55«aeo ASSESSMENT OF INTAKE ANO EXPOSURE LIMITS FOB WORKERS AND II - RADON DAUGHTERS IN THE OCCUPANTS CF A HCUSE » 1 IN AN FOR MEMBtRS OF THE PUBLIC ARE OUTLINFC. (OR1G.I. UNUSUALLY HUGH CONCENTSATICN OF AIKSCPHE ÊADCN. AU - RUNDO « J.: !»HA, J.Y.; ÎCOHEY. R.E. CR - ARGONNË NATIONAL LAB** IL (USA). 04480CO NU - ANL 79-65IPT.2I. PU - P. 13-20. RADIOLOGICAL IKE E NV IRCNHENT >L TESEABCT- OIVIS1ON. ANNUAL REPORT* 1W9. KT - AI»; EISMUTH 2 1*: CUILOINGS; DAUGHTER CRCCLCTSJ OECAY; DOSIMETRY: EXPERIMENTAL DATA: GAMMA SPECTRA; IN VIVO; ISCLATEO VALUES: LEAD 2HS LUNGS; HAS; PLLTCMUM 239; POLONIUM 218; RADIATION DOSES; RA010ACT1VE AEROSOLS: RADICECCLCGICAL CONCENTRATION: RAOCN 21ZI GETENTIOO AB - THE RESIDENTS OF A HOUSE HHICH HAS HIGH RAOCK CONCENTRATIONS CONTAIN EASILY MEASURABLE LEVELS OF HADON DAUGHTERS (TYPICALLY APPBCX. 400 8C OF IMCII. THE RESULTS OF THE MEASUREMENTS ARE KEPCRTEC AND SCME CALCULATIONS OF AesCRBEO CCSE TO LUNC. ANC OF T»E MO.IH OF 2I0P6 IN VIVC ABE PRESENTED. THE RELEVANCE CF T^E FINDINGS TO THE PROBLEM CF ASSAY OF PLU1CNIUM IN LING IS ALSO DISCUSSED.

2 23 223 (CONTINUED) RE - LUIS: R0-54B69I PERIOD FROM EXPOSURE TC FIRST DEVELOPMENT CF CANCEC ANC II - ESTIMATED RISK OF LIVER CANCER OUE TO ALPHA EMITTERS AND OUANTIFICATICN OF THE SENSITIVITY CF O-ILOBEN EELATIVE TC BETA-ALPHA EMITTING BARENT-OAUGHTER CHAINS: AN ADULTS ARE CF PRIMARY IMPORTANCE. CF LESEtf IMPORTANCE APPLICATION OF TH0R01RAST DATA. FOR THIS CANCER ARE THE DURATION CF THE RISK PLATEAU AND >U - NELSON. N.S.: ELLETT, ».«.: COOK, J.I).: HODGE. F.A. I WHETHER THE RISK IS BEST ESTIMATEC BY USE CF AN ABSCLUTE ENVIRONMENTAL PROTECTION AGENCY. WASHINGTON, DC). OR A RELATIVE RISK MCOEL. HEALTH EFFECTS ESTIMATES «OULO NU - ISSN 0013-9351. OE IMPROVED IF THE THOROTKAST CATA COULD BE ANALYZED TC PU - CNVIRCN. RES. AOE. THUS IT IS STILL IMPCRTANT TO REFINE THE THCRL'HAST OATA ON LIVER CARCINOMA FURTHER, IDENTIFICATION OF IR.F LATENT

227 227 (CCNT INUED > BE - LUI*: «0-S44Î3I INCLUDE TH-232 DECAY CHAIN RAD10NUCL1OES SUSPENDED AS Tt - ANTICIPATED RADIOLOGICAL IMPACTS FRCM THE MINING ANO DUCTS ANO RN-2Ï0 AND DAUGHTERS INITIALLY RELEASED AS GAS. MILLING OF THORIUM FOR THE NONPRCLIFERATIVE FUELS. FIFTY-YEAR DOSE COMMITMENTS TO MAXIMALLY EXPOSED AU - MEYER. H.R.; TILL. J.E. (CAK R10GE NATIONAL LAB.. TN I INDIVIDUALS OF 2.4 MREM TC TCTAL ECCY. 9.5 HPEV TC BCNE. USAI. HEALTH ANO SAFETY RESEARCH DIV.I. ANO 35 NREM TO LUNGS ARE CALCULATED TO RESULT FROM KELLEPMANN. H.J. -P). KE - DAUGHTER PRODUCTS; OC£E RATES; OUSTS: ENVIRONMENT; FUEL CYCLE; HUMAN POPULATIONS; IOAHO; LEAD 212: MILLING: MINES: MINING: BIOUIICN DOSES; RADIOACTIVE AEROSOLS; RADIUM 2?a: RADON 22o: THORIUM; THORIUM ORES: THORIUM 22H; THORIUM 23; *U - AN ANALYSIS HAS REEN COMPLETEO OF HYPOTHETICAL MINE-MILL COMPLEXES USING POPULATION AND «ETECOLOGICAL DATA REPRESENTATIVE OF A THORIUM DESCUOCE SITE IN THJ LEMHI PASS AREA OF 10AHC/WCNTANA. SOURCE TERMS FOR THE SITE 000030 j«7 2tl UCMIMJEOI L1106: BO-510700 DUNNING ET AL, iCHNL/NunEG/TM-1ÇO/vî , 1WS». THE5t VALUES REEVALUATION OF DOSE EQUIVALENT PER UMT INTAKE FOR ARE 5UGGESTEQ AS THE MCST SUITABLE FCR CALCULATING Tue 232TH. RADIOLOGICAL EFFECTS CF THCRIU» FLEL CYCLES. (AUTI-CCI. MEYER* H,R.; DUNNING. O.E. JR. (CAK RIDGE NATIONAL LAB.. TN (USA)I• 4832000 | S5N 0017-9078. HEALTH PHYS.

258 258 (CCNT1NUE0) R6 - LI022: '«-487631 232TH. OOSES TO THE GENERAL POPULAtlCN Is THE AREA T| - RADIOLOGICAL IMPACT CF THORIUM MINING AND MILLING. SURROUNDING THE SITE AK0 PCS TCPER AT 1 CN AL OCSES CUE TC AU - MEYER* H.R.; TILL* J.E.; BCMAR* E.S.: BOND* V*0*; MORSE* TAIL1NG5 PILE RELEASES ARE ALSC CALCULATED. L.E.; TENNERY* V.J.! VALCINTAS* M.G. IOAK RIDGE NATIONAL LAB.. TN). NU - ISSN 0029-S604. PU - NUCL. SAF. (MAY 19791. V. 20(31 P* 315-330. KÇ - FNV1PONMENTAL EXPOSURE PATHWAY, FEED MATERIALS PLANTS; HUMAN POPULATIONS! MINES; MINING: ORE PROCESSING; RADIATION DOSES; RAOIATION HAZARDS: RADIUM 22t; RADON 220: THORITES THORIUV CRESS THORIUM 232! USA AS - IMPLEMENTATION OF AN ALTERNATE FUEL USAGE SCHEME INVOLVING 233U WOULD RECUIRE VERY LARGE INCREASES IN 232TH PRODUCTION RATES* PRCBABLV NECESSITATING THE MINING OF THORITE (THSI04) FROM «ESTERN U.S. DEPOSITS. THIS ARTICLE REVIEHS CURRENT ESTIMATES OF THÇ EXTENT OF THAT RESOURCE AND ESTIMATES THE RADIOLOGICAL IMPACT OF OPERATING A THORIUM MINE AND MILL IN TH£ REGION. RADIOLOGICAL OCSES TO A HYPOTHETICAL 'AKIDALLY EXPOSED INDIVIDUAL LOCATED 1.6 KM FROM THE SITE ARE ESTIMATEO TC RE 2.4 MRF.MS | TO TOTAL BODY). 9.S MRENJ (TO BONE). ANO 35.3 MREMS (TO LUNGS). THESE DOSES ARE OUE PRIMARILY TO INGESTION AND INHALATION OF 220RN OAUGHTERS* 22BRA AND

265 265 (CCSTINUEOI "5 - L1019: 79-479944 TIMES THAT CP 226RA. 0R1NK1NG WATER CCMRIEUTES LESS ThAh T| - NORMAL DIETARY LEVELS OF 226RA, 228RA, JlOPB. AND 2I0P0 5« OF THE DAILY IKTAKE. EXCEPT IN SPECIAL AREAS. FOR MAN. AW - HOLTZMAN, R.n* DO - ARGCNNE NATIONAL L«e.* IL (USA). 0446000 NU - ANL--78-65(PT.2). °U - P. I 74-175. RAOIOLCGKAL ANO ENVIRONMENTAL RESEARCH DIVISION ANNUAL REPORT. JULT 1977 JUNE 1978. 1978. «i; - CONTAMINATION; DIET: CRINKING HATER; GEOGRAPHICAL VARIATIONS; HUMAN POPULATIONS; INGESTION; LEAD 2io; POLONIUM 210: RADIUM 226; RADIUM 228 AB - A BEVIEW OF THE LITERATURE ANO THE RESULTS CF SOME RECENT MEASUREMENTS HERE PRESENTED ON THE LEVELS IN MAN'S DIET OF THE NATURALLY-OCCURRING RADIOhuCLI DES 226RA. 228RA. 2I0PB* AND 210P0. THE MEAN INTAKES FOR STANDARD U.S. OIETS FOR THESE NUCLICES ARE TABULATEO. INTAKES IN OTHER COUNTRIES ARE SIMILAR TC THOSE IN THE U.S., BUT IN LOCALIZED POPULATIONS Tt-E 226RA INTAKE 1AY PE 8 CR MORE PCI/DAY. THE CONTENTS OF 226RA IN DIETS CHOSEN BY INDIVIDUALS RAfcGEO FRCM 0.4 TO 7 PC1/0AY. THE FE» DATA CN 228H4 SH0« INTAKE CF THIS KUCLIOE TC EE ABOUT 80» THAT OF 22F>RA, EXCEPT IN MCNA2ITE AREAS WHERE INTAKES CF UP TO lf.0 PCI/HAY 22BRA ARE REPORTEO. WHICH MAY HE 50 TO 100 269 ( (.CM INIJEO ) L I 0 I 8 : 79-4 766 16 LIVER. SPLEEN. LH LYM^h SCDgS. I I IAS CCNSIUthtO II-AT * CA5E nf MALIGNANT SCFT TISSUE TUMOR IN THF. L6FT UPpE" TUMOR WAS MALIGNANT SOFT TISSUh TU"C*- INCUCtD Z* TH- ARM INDUCED 9V TMOfiQTt-AST ADMINISTRATION. LOCAL IKJECTICN. I 1CH IK A*A . K. ) . ( IN JAPANESE ) • MQRI TA * TET SURC ! OHKISHl* VCSHlH I SA ; EMUR*, 1**01 TA P. 9 7 5-9 7B. APMS: BIOMEDICAL RAQICGBAPHV; DELAYEO RAO I AT [ON EFFECTS; MAN; NEOPLASMS ; PATIENTS; RAOIATICN iNJuntEs; GETEKTICN; THOROTRAST A PATIENT (A 6FT—YEAH-CLO MAN) HAC A MALIGNANT SOFT TISSUE TUMOR (FIBROMROANGIOSAHCOMA) IN THE LEFT UPPER ARM INDUCED BY AN INJECTICN OF THOFLOTRAST 3* YEARS AFTE* HAVING HA0 AN CPEN FRACTURE IN THE LEFT UPPER AFI" DY A SMELL. SOME GLOSS WAS OBSERVED IN THE SCAR TISSUES SCATTERED IN THE TU«CF. THERE WERE M AN Y Hno*N ANO FINE GRANULES OF VARIOUS SIZES. USING M ICRCAUTOGRAPHY ANO AN X-RAY MICROANALYZES, TMCTOTRAST hAS CERTIFIEO. IT «AS CLARIFIED THAT TRACH1AI. PLEXUS INJURY ANO PSEUDOANEURYSMA HAD SEEN SUSPECTED AT A MILITARY HOSPITAL AND THCROTRAST HAD OEEN INJECTED. THESE WAS NO SPECIFIC SHADOW IN TME

275 2 75 < CONT INUEO 1 RE - L1017: 79-473061 RUT LONG-TINE-CCUPSE CesE^VATICN SEE»«EC TC eE NECESSAHY T| - INJURY OF THE RIGHT LEG LONG TERM AFTER THOROTRAST IN FUTURE CONSIDERING A POSSIBILITY GF ITS EX ACEHRAT I Oh. INJECTION* (ICHIKA*A, K.), (IN JAPANESE). AU - ITO. VUZO: TAGUMA, KlYCHlKC! VAT5UZUKA* WlTSUC (NATIONAL TÛSE1 HOSPITAL. SHl^uCKA (JAPAN)). NU - ISSN 0030-SQ01. PU - SE IKE I GEKA. (SEP l?7e). V. 2*9(10) P. 9 ' i -9M . KE - BlOMtiOICAL RADIOGRAPHY; DELAYEO CADIATION EFFECTS; LEGS; MAN: PATIENTS; RAOIAT ton INJURIES; RETENTION; THOROTRAST Afl - A PATIENT (S7-VEAR-0L0 MAN) HAD CPEN FRACTURE OF THE LEG DUE TO A BULLET WOUNO PENETRATING THE RIGHT LEG IN 19*1. AND HAD ARTERIOGRAPMV FROM THE RIGHT POPLITEAL FOSSA AT AN ARMY HOSPITAL IN ;<342. HE COW PL AI NED OF PAINFUL SWELLING RANGt NG FRQM THE INWARD 5IT? OF THE RIGHT FEMUR TO TME POPLITEAL FCSSA IN 1977. AS A RESULT OF THE EXAMINATION USING A SCINTILLATION CCUNTER. IT «AS DIAGNOSED AS AN INJURY IT THE PIGHT LEG LCNG TERM AFTER THOROTBA5T INJECTION. THERE WAS KC DEPOSITION OF THOROTRAST IN THC LIVER. THE SPLEEN. OR THE EPIGASTRIC LYMPH NODES. HlSTOPATHCLCGtCALLV, THERE WAS NO FINOING OF MALIGNANCV BUT GRANULCMA. THE FINDINGS ON THE POSTOPERATIVE EXAMIKATICN «ERE RESTCRED TC TME NORMAL*

276 276 (CCNTlNUED) PE - L 1017: 79-4/3060 GETA6LES TI - DOSES FQR VARICUS PATHWAYS TO MAN 8ASE0 Or UNIT URANIUM 234; URANIUM 2J5 ; URANIUM 23Ci VE IT CONCENTRATIONS OF RACICNUCL IDES PERTINENT TO CONCENTRATIONTHIS REPORT GIVES OSF DOSRAOE ICMjC TABULATIONL I OE S LS FCR UTtC Ht fcNCGU OECONTAMINATION ANO DECOMMISSIONING Of PROPERTIES. ÏN THE OECCM*! SSI CM NG CF f-E AL £S CCN TAM INATEO • I TH AU - HlLL* G.S. URANIUM AND THORIU» CRES AND RESIOUEÇ REPCtlE OR - OAK RIDGE NATIONAL L*e.. TN (USA). «6^2000 HAT BE PATICED TO KNCaN AIR. SCIL AND «A TER : DCSES NIJ - ORNL/OEPA--7. CONCENTRATIONS. EXPCSUHE TIKES. A C IhTAK ES TC E5T IMATE PU - MAR 1979, M P. THE TOTAL RAOIATICK 005E FCR 1KDI I EXFCSEO T C THE NO - AVAILABLE FROM NTIS** PC A0*/MF A01» FACILITIES. THESE DOSE ESTIMATES AY BE SEO IN *.£ - ACTINIUM 227; ACTINIUM 228; AIR; fllSMUTH 210: BISMUTH DEVELOPING CRITERIA TO OETEBXISE ATE KEMEC 211: BISMUTH 212; BISMUTH 214; CATTLE; CONTAMINATION! ACTIONS FOR RETURNING THE PROPERTIEFPPCPPS TC 1 SEFUL PUB DECOMMISSIONING: OECONTAMINATIQN: DOSE COMMITMENTS; INO FOR ESTABLISHIKG RESTRICTÎCNS FCt SUC >• USE. DOSIMETRV: DQTNKLNG WATER; ENVIRONMENTAL EXPOSURE PKTHMAV; GXPER I MENTAL DATA; EXTERNAL IRRAOIATICN; P ISHES ! FOOD CHAINS: GROUND «ATER; HUMAN POPULATIONS; INGESTION; INHALATION; KIDNEYS; LEAD eio; LCAO 211: LEAD 212; LEAD 214; LUNGS; MEAT; MJLK; NUCLEAR FACILITIES; PLUTONIUM 236; PLUTCNIUM 239; PCLCNIU** 210; PCLCNIUM 2l*î PCLONlUM ?|fl; PROTACTINIU" 231; PROTACTINIUM 234: RADIATION 00SES ; PAD10IS0T0PE5; RADIUM 323', RADIUM 224; fcADIUM 22C:; PAUlU* 22«î MAOCN 219: RADCN 220; RAOON 222Î SKELETON; SCILS; SURFACE WATF.PS; SUR FACES; TABLES; THOPIUM 227Ï THCRIUM 2281 THQRlU" 230*, THCKIUM 2311 THOR tU»* 232; THOPIU" 21*; • KU. K < z O D lu UJ^ u UJ U 4 U Z tt 4 • • —. .-»- uj (D z o -t *- a t- • Jl Z Z (/) 3" Ul V) Ul Uï -J O 4 O OH J UJ \li H** jut- • LL —u in JI a u.»- oua>zrz»~— zo < 4_-u; 4. Z -- z u< — u z

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o za 3bb t CC M INUFD 1 HE - L0S07; r7-2'i»B9*B ACCOUNT THE GMfATEC ICxICM*' CF PLLICMl»1 RELATIVE TC RADIUS. THE RELATIVE TCMCITY CAN eE Ev.»LU*TED FUCM Tut T| - PROBLEMS IN RADIOLOGICAL PROTECTION INVOLVING ALPHA UA TA CN OSTECSARCCWA INCIDENCE IN AN I K #L S . ti C T t- ME TMCDS EMITTERS IN HONE. AU - DOLPHIN, G.W. «NATIONAL RAO1OLOGICAL POCTECTICN PCAPO. OF P.1SK ESTIMATION Afit GIVEN AND CKMlClSEC IN THE PAPtR. HARWFLL (UKII, 45Q2 700 IN FUTURE RECCMMENOATlCNSi IChP «ILL NCT USE The CRITICAL NO - AEO-CONF 76-430-004. ORGAN CCNCEPT AK-Q THE L*TE EFFECTS FRO" ALFHA EMITTERS PU - 1976. 16 ». DEPOSITED IN ORGANS CTetfl THAN THE Ut-NE «ILL HAVL TC dL NO - 4 TAUS.: «ITM REFS. TAKEN I NTC ACCCUNT IN SETTING H*X[NUV PERMISSIBLE ANNUAL CO - 2. INTERNA" 1NAL SVMPCSIUM ON BIOLOGICAL EFFECTS OF R A- INTAKES. THE IMPLICATILNS CF THIS ANC CThEC PROPOSED 22A. NEUHEfiLERG/MUENCHEN. GERMANY, F.R. 20 SEP 1976. CHANGES IN ICRP CCNCEPTS ARE DISCUSSEC. (CKlG.l. KF. - ALPHA OECAV R Ao i c i SCTC P£S : EEAGLES; BIOLOGICAL RADIATION EFFECTSÏ BONE CELLS: eCNE SEEKERS: CARCINOGENESIS ; CRITIC AL ORGANS: OATA; tCRPi MAN: OSTEOSABCOMAS; PLUTONIUM 239; PAQIATION DOSES: RADIATION PROTECTION: RAÛlUM 226: SAFETY STANQARDSÎ SKELETON; TCXICITY A» - QUANTITATIVE OCSE/EFFECT RELATIONSHIPS FOR HUMANS EXPOSED TO ALPHA EMITTERS CAN ONLY BE ESTABLISHED FROM OATA ON MU«ANS EXPO S£ D TO THIS TYPE OF RAO1 AT ION. TH£ BISK OF RONE SAPCCMA FBCM EXPCSURE TO PLUTCNlUM-239 MAY RE C5TAULISHE0 FROM THE CATA ON THE HU*AN CASES EXPOSED TO PAOtUM-2?6 ÇITHÇR PV CONSIDERATICN OF THE RADIATICN OOSE TC THE CSTCCPRTGENITCK CELLS CR BY USE OF THE AVERAGE HCNF 00 SE TOGE TMER HITH A WCO ÏF Y ING FACTGP TO TAKE 1 NTC 000031

362 362 CCCNTINUEO » RE - L080?: 76-293703 TIME DEPENDENCE; YTTRIUM so; IMRAVËNCLS I TI - OOSE. OOSE HATE AHO «CE PARAMETERS IN ANALYSIS OF RISK RAOlU** 2Zt FPO« RONE-SEEKING HAC IOSUCL10ES: AN EXTRAPOLATION OF LO» RADIATICN-INCUCED PRIMARY GONE SiCiCMAÇ (PCS) AND Llf=E- LEVELS. SPAN SHORTENING (DELTA) «ERE STuOIiO AS A FUNCTION OF AU - MQMENI. M.M.: WILLIAMS. J.K.; RCSENPLATT. L»S. < OOSE. DCSE SATE ANC TIME IN BEAGLES FEC FRCM « IOGESTAT I ON CALIFORNIA UNIV.. DAVIS (USA). RA010BI0L0GY LAB.). TO 1.5 YEARS OF AGE DIETS CONTAINING 90S* CJ. 2 IN 1132000 EQUILIBRIUM »ITH ÇC>« CR ADMINISTERED îîtR* CL2 IN EIGHT OR - INTERNATIONAL ATOMIC ENERGY AC-EKCY, VIENNA (AUSTRIA): SEMIMONTHLY INTRAVENOUS INJECTIONS STARTING AT 2, 4 OR 14 WORLD HEALTH OPGAN1ZAT ICN. GENEVA (SWITZERLANOI• 3294000; MONTHS CF AGE* PBS AND DEL TA FRC 905P.+ÇCY AND 226£A «ERE DEPENDENT ON (NTERACTICN CF DOSE RATc. DCSE. AGE A NO TIME NU - IAEA-SU—202/415.; ISBN «2-0-010 176-3. AFTER THE AC1MSTRATICN CF THE R AC IOAC T I V I T IE S . AND MODE PU - RIOLOGICAL «NO ENVIRCS"ENTAL EFFECTS CF LOW-LEVEL OF ADMINISTRATION »ITH A DYNAMIC NCN-LihE AC CRGAN SYSTEM. CADHTION. PROCEEDINGS OF A SYMPC5IU" ON BIOLOGICAL THE SKELETON* INCIDENCE QF PBS FROM ÇOSBtÇCY AN0 22tfiA EFFECTS OF LOW-LEVEL RADIATION PERTINENT TO PROTECTION OF • AS CALCULATED FRC** LIFE-TABLES. PfiCe*eiLITY CF CHEATER MAN AND HIS ENVIRONMENT ORGANIZED 8V THE IAEA AND THE WHO THAN IX PQS INCIOENCE lAS NORMALLY OISTPieLTED «ITH ANO HELD IN CHICAGO. 3-7 NOVEMBER 1S7Î. VIENNA. IAEA. RESPECT TO DOSE ANC AGE. DELAY PEPICD EETfcEEN EXPOSURE 1976. V. J P.197-209. PROCEE' INGS SERIES. ANO TUMCUfi INCIDENCE hiS SUGGESTED TC El FRCPCfiTICNAL TC CO - SYMPOSIUM ON BIOLOGICAL EFFECTS CF LOW-LEVEL RADIATION TIME TO IX INCtOENCt OF PGS ÏTC). FOB Ç0SC»90Y DCGS. PERTINENT TO PROTECTICN OF MAN ANO HIS ENVIRONMENT. ESTIMATED TO WfcPE 9.4 YEARS. 5.1 YEARS. AND I . * ¥E*fiS ^OPl CHICAGO. ILL.. USA. 3 NCV I

362 (CCKTINUEO) 363 RESPECTIVELY. PAOÏATICN-INCUCEO LIFE-SPAN SHORTENING WAS ESTIMATED FROM '•PRACTI CAL SURVIVAL AGE' •» AGE AT SX RE - LOdor: 7*-?ej6Çj PCPULAT ION SUR VIV AL. AT A MIX. I MUM OCSE RATE DSUFL< MAX) QF TI - HODGKlN«S DISEASE FCLLC»ING THORIUM ClCHlOE AhOICGPAPHY. 2.5 RAD/DT 905O*90Y AND Z26RA WERE EQUALLY EFFECTIVE IN AU - GOTLIEO. A.I.; KIRK. M.E. (MCGILL CN IV, , MONTREAL. OUEBEC REDUCING LIFF-SPAN. BUT FQR DSU0< MAX)> 2.S RAO/Û» 90SR* (CANADA). DEPT, OF PATHCLCGY»; HUTCHISON. J.L. (MONTREAL 90V WAS MORE EFFECTIVE THAN 226RA. A OOSE OF (00 RAOS FOR GENERAL HOSPITAL* GUEUEC (CANADA) I. ; 432520C RADIUM »ND 1700 PAOS FCFI STRONTIUM INTEGRATED TO TSUD( PU - CAN. MEO. ASSOC. J» <4 SEP 1976). V. 1]5(S» P. 433-434, MAX)*1^,S YEARS 010 NCT INDUCE A OETECTABLE LIFE-SPAN NO - X? «EFS. SHORTENING, (AUTHOR). KE - RiCMEoiCAL RADIOGRAPHY: CLCOD VESSELS; DELAYED RADIATION EFFECTS; HEAD; HOOGKINS OISEASE; MEN; RET ICULOENOOTHELtAL SYSTEM; IHCRCTRAST AD - HOOGKIN»S OISEASE CCCUCPED IN A 5J-YEAR-CLÛ «AN 9HC, 25 YEARS PREVIOUSLY, HAD UNOEt-GONE C£KEEB*L ANGICGRAPhY. FCR WHICH ThOHlue DIOXIDE SLSPÊNSICN (THCRCTRAETI «AS USED. DE PO SITS OF IMCCIU" CICMCE »E(-E NCTED IN HETICULCENOCTi-iELIAL CELLS IN VAP1CLS LOCATIONS. AN ASSOCIATION t'tT«fFN IMCSlO»1 C)C*IDt ACVjNISTRjlTJCN AND THE SUeSEGUENT OEVELCPMENT Cf "ALIGNANT tl-CUHS ANC NGOfLASTU HfcWATOLCGIC OlSCMCrtJS HAS Ff-£VlCUSLY CECN «Fk>UK TF3. ( AUT hOR I • « i/l £ lA • D Jl ^ r- < U.CT • £ -» • loi— UU UUJJ

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I I J60 {CCNT JNJEOI L0B01: 76-2812PP KC - CAftClNOUENESIS; DALtiHTEP FUCCUCT s: ucse P-AIE. = ; DCSE- LUNG CANCER I NDUCEO IN RATS BV PA DON ANO ITS DAUGHTER RESPONSE RELATIONSHIPS: [N-MALAT1 ; NUCLIOES AT OIFFERf.NT CCNCENTR AT ICNS . LUNGS; QUANTITY RATIO; PACIAT t CN DLSES ! KACLN ; RAT b (IN FRPNCH), CANCELS CU POUUCH PROVOOUeS CHEZ LE BAT PAH AH - IN PHEVIOUS EXPERIMENTS CN HATS NEAPLY ALL Iht ANIMALS LE OAOON ET SES OE«CE*DANT S * DIVERSES CONCENTRAT IONS . INHALING PACDN ANC MS DAUGHTER SUCL lOtS IN HOH CHAMEAUO. J.; PERRAUO . R. (CE A , SERVICE MEDICAL. PU1MCNA&Y CANCERS. IN TME DIRECTION DES PRODUCTIONS. RAZE5 • FRANCE»; MASSE. R. ". CONCENTRATICNS DEVELCPEC eccNCh OCEÉ-EFFËCT &ELATICNSHIP NENOT, J.C.; LAFUMA, J. (CE* CENTRE D •ETUDES NUCLEAIRES KAL PARAMETERS: c E^PcRlMENTS DFSCR1HEO HERE. THE DE f-ONT NAV-AUX-RCSES, S 2 (FRANCE). DEPT . DE PROTECTION». •AS STUDIED AS A FUNCTION OF SEV »HCt- »£BE LC»EP ThAN IK : 129*100 INFLUENCE Of- TCTAL INHALEO OC5ES Ct CF lht CONCENTRATION INTERNATIONAL ATOMIC ENERGY AGENCY. VIENNA (AUSTRIA); L I E> lu* tilTt- ITS DAUGHTER THE PREVIOUS EXPERIMENTS; INFLUE 1CN CF UJilLV ANQ TCTAL WORLD HEALTH ORGANISATION. GENEVA (SWITZERLAND). 3?9*000! OF THE GAS ANC ITS STATE CF EGuI b^HtOOO £t IN 7f-E F(.eC^>e^Cï NUCLIOES; INFLUENCE CF THt LJURAT LAT1VE esPCSUftE. THE IAEA-SM--302/402.; I SEN 92-0-013176-J. EXPOSURE. THgCE WAS A DEFINITE. I «IOLOG1CAL AND ENVIRONMENTAL EFFECTS OF LOW-LEVEL CSITICN ANC CA1LY CCSE OF CANCERS AS A FUNCTION CF CU*U CF THt CCNSlUtflAHLt RADIATION. PROCEEDINGS OF A SYMPOSIUM ON BIOLOGICAL RESPECTIVE EFFECTS CF ACTIVE Dt° EFFECTS CF LOM-LEVEL PACIAT1ON PERTINENT TO PROTECTION CF LA I 1 ChSt- IP IN THE ARE SHOWN OUME CLEARLY. IN VIE MINERS. IT SÊEKEC »CKTH MAN AND HIS ENVIRONMENT ORGANIZED BY THE IAEA AND THE KMC IMPORTANCE CF ÏH£ CCSe-EFF£CT KE AND HELD IN CHICAGO» 3-7 NOVEMBER 19 75. VIENNA, IAEA. RADIATION PfiCTECTICN CF l,R A? CIWENTAL FINDINGS 1976» V. 2 P.223-228. PROCEEDINGS SERIES. «HlLE TC CCMPARE THfcSE: DIFFERENT CAL STLCIES "*OE IN THIS SYMPOSIUM ON BIOLOGICAL EFFECTS CF LO»-LEVEL RAOIATICN • ITH THE RESULTS CF EPIDEWICLCGI PERTINENT TC PROTECTION OF MAN AND HIS ENVIRONMENT. CATEGORY CF" hCf-KEfS. ( AUTHfR >. CHICAGO, ILL.. USA. 3 NCV 1975.

369 JG9 (CCNTINUED) CC - L072*: 76-?78687 TG PEOPLE THE INCIDENCE CF Q«TEC S APCCMAS USING DATA T I - EXTftAPOLATlON OF RAOI AT ION-INDUCEO TUMOUR 1NCIOENCE FRO* DERIVED FRCM MICE AND DCG5 INJECTED »ITH 22t.PA, MAXIMUM ANIMALS TO MAN. (OSTECSARCCMAS FRCM INJECTED 226PA.) CUMULATIVE INCIDENCE RATES Ï»CIR) FCh C5TECSAHC0MA «ERE AU - ROSENBLATT » L. S. ; GCLC*"*N, M. ; PCCK , S* A. ; «C«ËNl. M.H. ( COMPARED FCR THE ANIMAL SPECIES ANC IT »Ag CESÊRVEC THAT CALIFORNIA UNIV.. O*VlS (USA). RA0ICBI0LOGY LAD.). THE INCREASED 1NJËCTE0 ACTIVITY (SCI/KG) RECUlPEO Et THE 1 132000 MOUSE RELATIVE TC THE CCG TC PRODUCE AN EQUIVALENT MCIH OR - INTERNATIONAL ATOMIC £N£RGy AGENCY, VIENNA (AUSTRIA): COULD 8£ EXPLAINED BY THE LESSEE BEUMUN OF 226RA «Y WORLD HFALTH ORGANIZATION* GENEVA (SWITZERLAND). 324 4 00 0 Î THE MOUSE, SINCE Tt-e DCC;MAN BETENTICN CATIC »AS 0994000 APPROXIMATELY 10 IT »AS POSTULATED THAT MAN WOULD REQUIRE NU - IAEA-SM—202/S22.; ISBN 92-0-0 I 0076-7. APPROXIMATELY 10 TIMES AS MUCH INJECTED Z2fcRA/KG AS THE PU - BIOLOGICAL AND ENVIRONMENTAL EFFECTS OP LOW-LEVEL DOG FOR EQUIVALENT MCIR. THE AUTHORS HAVE AMPLIFIED THIS RAOIATION. PROCEEDINGS CF A SYMPOSIUM ON BICLCGICAL APPROACH IN AN ATTEMPT TC 5CALE *CIK IN FÉCPLÉ FCR EFFECTS OF LOW-LEVEL RADIATION PERTINENT TO PROTECTION OF nsTEOSARCOMA 1NCUCT1CN FROM INJECTEO 23ÇFU. USING ThE M*N ANO HIS ENVIRONMENT ORGANIZED BY THE IAEA AND THE *HQ RATIOS: (PU/RA)"AN APPRCXIMATELY ECUAL TC (PU/KA>OCG AND HEXO ÏN CHICAGO* 2-7 NOVEMBER 1975. VIENNA. IAEA, APPROXIMATELY EQUAL TO (PU/RA) MOUSE. THESE HATILS «EPE 1976. V. I P. 237-241. PROCEEDINGS SERIES* CALCULATED FRCM PfiCPCKF(CKALITï CCN5ÏANÎS» P*S, CfcfilVEO CO - SYMPOSIUM ON BIOLOGICAL EFFECTS CF LOW-LE.VEL RADIATION FOR EACH SPECIES FCR EACH ÊADICNUCLIOE. »HE«E P = D X PERTINENT TO PROTECTION OF MAN AKO HIS ENVIRONMENT. TSU1(E) X A; «HERE 0 = INJECTED ACUVIIV IN NCI/KG tC CHICAGO. ILL»» USA. 3 NOV 1975, PRODUCE A 50» MCIP. TSU6ÏE) = THt£ EFFECTIVE 1-ALf-LlK IN «F - CARClNOGENESIS; DELAYED RADIATION EFFECTS: DOGS; flCNC;. AND A = FRACTIONAL SKSLETAL UPTAKE. F FCC PU-PCEPLE EXTRAPOLA TION; FORECASTING; INJFCTICNÎ M*N; MJCEI "AS ESTIMATED AT IT3 FKC THF MAS! DUG *M IBZ FPCM THE OSTEOSAPCOMAS; OADIU" 22h HAN:MOUSE CCPACISCN. FPC«* THESE VALUES ÎT MAS ESTIMATED AB - A METHOD w*5 PRESENTED ËY THE AuTHQRS EARLIER OF SCALING 000031 THAT O FCH A 50X MCIP FCR 23SPL IN MAN »J$ 3.3 NCI/KG. IT

381 381 < CCNT 1 NuEO) RC - L0719: 76-265567 A PLUTONIUM-RADIUM TCXlCïTY BATJJ IN THE DCG. THfc Tl - SO«E SIMILARITIES OF KACIU" ANO PLUTONIUM TOXICfTY IN THE VALIDITY CF TMl 5 cETt-CC IS CCNTINCENT C*. SIMILAR TARGET BEAGLE AND MAN* (EXTRAPOLATION OF 226RA* 226RA, AND 239PU TISSUES FOR UOTH PU AND HA AND APPPUXJVATELY ECUAL f.ÛE»S FROM OOGS TO MAN.) FOR PU RELATIVE TC R* IN eCTH WAN ANC THE CCC. THUS. AU - TAYLOR* G.N.: JEE • W.S.S*! MAYS. C*W, (UNIV. OF UTAH ALTHOUGH THE R AC I CSËN S I T I V IT Y MIGHT EE S I GM F IC AN-TL Y COLL. OF KEOICÏKE. S*LT LAKE CtfYi. OlFFE^ESI * 7 Hi £l«i;PClN7£ »|TH(N A GIVE WEBSTER» S.S. (ED.). 1 I SSLE IN KAN ANC ou - HEALTH EFFECTS OF PLUTONIUM ANO RADIUM. SALT LAKE CITY. TME ANICAL MUOEL MUST NtCtSSAHlLY L'E C "PAP*TIVE. THE UNIV. OF UTAH. 1976. F. 523-S36. DECREE CF PAPALLELIS" IN THE HAOIu»*-IN CCEC SYKCRLHt 5 CF *C - SCE CONF-7510*3--. MAN ANO THr eFAGLÉ ARE £XAV[NCO IN C^C C TC ASSESS THE CC - WORKSHOP ON THF BICLCGICAL EFFECTS AND TQMCITv OF Py 2"><3 noACT1CAHIL I TV CF ESTIMATING Pu RISK l AND RA ?2ft. SUN VALLEY. IDAHO. USA. 6 CCT 1975. I)F A "u-RA TCklCIT* WATIC IN TME Fc^tL «F - MEAGLES: BIOLOGICAL BACIATION EFFECTS; RCNE TJSSUF",; DiSToiouTioNj ones: CCSE-BESPCNSE RELATICNSHIPS; EXTRAPOLATION: EYES; INTERNAL IRRADIATION: LIVER; M*N; MELANOMAS; NEOPLASMS; CSTECSAPCCMAS; PATMCLCGICAL CHANGES! PLUTONIUM 22<;; R AO IOSEN S IT I V I T V ; CADIUM SIT,: RADIUM ?2B; TOXICITV AM - THE VALUE OF MANY TCXLCITY STUDIES. IKVTLVING VAPTOUS LAPEWIMENTAL AN|MALS. IS CCNT1NGENT CN "Ci bfllAf'LY THE HAT* C»N HF RF.LATÇO TC "AN. AN EOUATIfN HAS UEÉN PROPOSED f'C" cxTp«DnLATI NG THF PU SYMIPfl^F f-'fiC" HCG STU0Ir3 TO ^AN. |T r«.">L0r5 THt EeTENÇIvf. Hu"tN »AJ.U« FXDfPlENCE INC OOOOll -» >- au 1 •- -3

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JOZ- N^KZ 396 Be - L07M.' 76-251*12 Tl - MODEL FOB THE 2Z*R*-CRCT1 *CTICN EFFECT. Au - GROER» P.G.; MARSHALL* J.H. OR - ARGONNE NATIONAL LAB.t ILL. (USA). 0**8000 NU - 1U.» 75-601 PT.2 I . PU - PADlOLOGtCAL AND ENVIfiCNMENTAL RESEARCH DIVISION ANNUAL egPORT, JULY 197* — JUNE 1975. 1"375. P. 39-42. KE - ALPHA PARTICLES: ANIWAL CELLS! EICLCGICAL RADIATION EFFECTS; BIOLOGICAL REGENERATION; BONE TISSUES: CHILDREN; DOSE PATESÎ MAN; MATHEMATICAL MCCELSI CSTEOSARCO«AS ; RADIATION DnSES: RlOlUa 22* AU - IT »AS P0INTEO OUT THAT FOR A FIXED TCTAL DOSE THE OBSERVED INCIDENCE CF BCNE SADCOMAS IN GERMAN CHILDREN AND AOULTS EXPOSEO TC 22ARA WAS HIGHER THE LOWER THE DCSÉ PATE. TWO MATHEMATICAL MODELS THAT EXHIBIT A PROTRACTION EFFECT ARE PRESENTED IN THIS REPCRT. eCTH MCOELS REPLACE CELLS KILLEO BV ALPHA RAOIATION WITH NORMAL ENDCSTEAL CELLS. THIS REGENERATION CF CELLS INCREASES THE TCTAL NUMBER DF CELLS AT RISK iNO LEADS THUS TO THE PRODUCTION OF MORE TUMOR CELLS CURING THE LCNGER TIME PERIOOS CORRESPONDING TC THE LCKFR OOSE BATES.

• OS 405 I CCKT1NUEDI RE - L0705: 76-228363 AND OF 726 CCMfiCLS CCUGHLY **7CHEC fcP >ce *sC SE*. ArsD Tl - THORIUM DIOXIDE EFFECTS IN MAN: ED1DEMIOLCG1CAL . THE STATISTICAL ANALYSIS PERFORMEC CN IHE RESULTS r-AVE CLINICAL. AND PATHCLCCICAL STUDIES (EXPERIENCE IN SHOWN THAT THE INCIOENCE CF MALIGNANCIES IN GENERAL. PORTUGALI. PARTICULARLY OF ACLTE LEUKEMIAS ANC «ALIÉNANT NEOPLASMS AU - SUVA HORTA. J. DA; CAVCLLA OA MCTTA. L.; TAVARES. M.H. OF THE LIVER AND CF LIVtt FIPHCSIS (LIVER •'CIfRHCSIS"'I (FACULTY OF MEDICINE. LISBON!. WAS SIGNIFICANTLY HIGHth AMONG THE TPACEC THCRCTHAST PU - ENVIRON. RES. (CCT 197*1. V. 8(2) P. 131-159. CASES THAN AMONG THE CCNTPCLS AND THE CENE^AL FCfiTLC-UESl KE - BIOLOGICAL RADIATION EFFECTS! DIAGNOSTIC TECHNIQUES: POPULATION. EVEN ALLCwlNG FOR THE PECULIARITIES OF THE EPIDEMIOLOGY; LEUKEMIA: MAN; NEOPLASMS: PATHOLOGY; DISEASED SERIES. AFTEU CCCRECTION CF THE RESPECTIVE OEM,. PORTUGAL; OEVIEWS; STATISTICS: THORIO» OXIDES: THOROTRAST RATES BY A CALCULATED FACTCR. THE M» »Cf FHCLCG1C AL AS - THE PORTUGUESE THOROTRAST SERIES COMPRISES 1230 TRACED LESIGNS FOUNO IN PATHCLCCICAL STUCIES CF THIS SERIES ( INDIVIDUALS OF A TCTAL CF 2*32 WHC RECEIVED THOROTRAST AUTOPSIES AND BIOP / IESI ARE LOCAL GR'NULCMATA OEVELCFEC FOR DIAGNOSTIC PURPOSES BETWEEN 1930 AND 19SS, AND HAVE IN THE TISSUES »HEFE THE OfiuG HAD BEEN SP1LLE0. LIVEG BEEN FOLLOWED SINCS THEN. OF THOSE. 1039 RECEIVED THE FISROSIS. ANC LIVER TUVCRS. CF THESE. THE MOST FRECUENT ORUG SYSTÇMICALLV (MCST OF THEM FOR CEREBRAL ANGIOGRAPHYI TYPES FOUND ARE HEKASGICENDOTHEL1C»As ANC . AND 191 LOCALLY. AMCNG THE 1230 TRACED CASES. 901 CHOLANGIOCARC1NOMAS. A MULTICENTR1C HEKA»CICENOOTHEL1OMA INOIVIOUALS HAVE D1E0 \JP TO 31 DECEMBER 1971. 23 FROM WAS FOUNO IN THE RETICULCENOCTHELIAL CSGANS IN 3 CASES- FATAL BLOCD OYSCRASIAS (12 OF WHICH WERE ACUTE LEUK£M|AS| BONE MARRCw LESIONS FCLNO HAVE BEEN LELKEKIAS CR APLASTIC • 10* FROM MALIGNANT TUMORS, 6« CF «HICH »ERE LIVER ANEMIAS. THE AUTHCRS CONCLUDE THAT THCACTRASÏ WUST HAVE TUMORS. THS MEMANGICENDCTHELIOMAS BEING THE MOST FREQUENT BEEN THE CAUSE CF SUCH PATH0LCG1CAL CCNSECUENCES. HlSTOLOGICL TYPE FCUNO; 23 FRO» LIVER CIRRHOSIS ANO 13 PRDOADLY THROUGH ils RADIOACTIVITY, ANC IHEREFCRE SHCULO FROM THE LATE EFFECTS OF CERVICAL GRANULOMATA OCCURRING AFTER CERF.1OAL ANC ICCCAPHY. THE FCLLOw UP OF THESE CASES NOT OE USED IN HUMAN 0E1KGS. (AUTHJ.

«06 406 t CONTINUED) RE L0703! rS-22363.4 HTMIN •- S.C. CF THE ECUAIICN Kt 6EACLES. THIS SUGGEST Tl FRACTIONAL RADON RETENTION IN BONE. THAT SKELETAL ON/RA RATIOS AS A FUNCT1CN CF TI»E MAY BE MAYS, C.V.; LLOYD, B.C.: VAN D1LLA, M.A. (UTAH UNIV.. SOMEWHAT SPECIES INOEPENCENT. THEREFORE. THESE RATICS SALT LAKE CITY (USAI. RADLCBICLCGY OIV,,, 66S0OO0 DEPEND ALMOST EXCLUSIVELY UPCN THE TIME FCLLCwlNG KAOIU PU HEALTH PHYS. (NOV 1( 1-ESUP(-O. 13 1 T) ) AT T DAYS OESCPIPES THE DEPENDENCE CF THE RN/RA RATIO IN THESE RONES UPON TIMF AFTER ADMINISTRATION, ANO WAS SHCWN TO 8f INOEPFNOENT CF »G6 AT INJEOICN OH RELATIVE INJECTED ACTIVITY. TH|S EQUATION ALSC APPEEARS VALID FOR DOGS THAT RECEIVED THFIR RADIUM IN SI* EOC'AL INJECTIONS iPACEC) OVER A «TRICO CF ?B0 DAYS. WHEN T IS CONSIOERCO AS TIME AFTER M|D-1 N JEC T I CN. AT LFAST »HEN THE T I «*E AFTER MIO-INJFCTION EXCEECS THE CURATICN OF INJECTIONS. CCMPARISCN OF RESULTS fCR DCGS WITH THCSE RPCCBTEC FOW MICF. RATS. CMINCILLAÇ, ANO HUMANS SHCwCO THAT ARCUT 69t OF THE INDIVIDUAL VALUES fCB THESt CTHEK SPECICS WEKE 41 J BE - L0621: 75-209710 TI - DOSE TO ENOOST EAL CELLS ANC RELATIVE DlSTfUHUTIÛN FACTORS FOB 0A0IUM-?24 AND PLl.TCNltjw-ZJ'S COMPARED TC RADIU«-226. ( INTERNAL IRRAOIAT1CN CF M *N . I AU - MARSHALL* J.H.; GPCEC. P.G.! SCHLENKEP. R. A. Qp - APGONNP NATIONAL LAB-. ILL. (USA). 044«OOO NU - AML—75-3

4 IS 4 1 <9 HE - LQM*: 75-1S0519 BE - L06I»: 75-190515 TI - RADlDCHEMICAL AND RAD I QECOLOG1CAL STUDIES ON BRAZILIAN TI - FATE OF INHALED RAOCK ffCCENT. (220RN. 228TM.I ' AREAS OF HIGH NATURAL RAOIATIDN. PROGRESS REPORT, JULY Au - ALEXANDER. D.R. 19Î3--AUGUST 1974. (PCPLLAT1ON STUDIES AND EFFECTS CF OH - COLOP-AOC STATE UNIV.» FCPT CCLLZNS IUS>J. TMESIS (PH. 0.» 212 PB IN Alfl OF MQNAZITE ORE »ILL OS CHRCMCSCE . 1822000 ABERRATIONS OF PERSC^^EL•I PU- 1974. e7P. AU - 0ARCINSK1. M.A.; RlBEIRO. C.C- KG - UNIVE05ITY MICHCFILKS C6DER NO. 7E-«B7T. 00 - RIO OE JANEIRO UNIV. (PPAZID. INSTITUTO DE BIOFISICA. KE - AEROSOLS! ALPHA SOURCES; BIOLOGICAL HALF-LIFE» DAUGHTER SS29360 PRODUCTS: INHALATION; HAK; PARTICLE SWE; RACICNUCLIOE NU - C00--34B9-7. KINETICS; BAOCN 220; RESPIKATCH- STSTE»; T^ORIW» as PU - 1974. 7 P. •CE - BIOLOGICAL RAO (ATI CN EFFECTS.* G*A7IL Î CHRCWOSCVAL ABERRATIONS* CHRONIC IPRAO I AT 1ON ; CYTOLOGY : ENVIRONMENT ; GENETIC RADTATION EFFECTS; HEALTH HAJARD5Î HUMAN POPULATIONS; INHALATICN: INT6RNAL IPPAOIATION; LEAD 212; M ILL1NG: MONAZITES: NATURAL RADIOACTIVITY; PERSONNEL ; RAO 10ACT IVE ML NEPALS

2 425 RE - LOftOe: 7f»-17Slftft L0605* 75-16C775 TI - FATE ClF INHALED RAOCN PPCCENY, (222RN HEALTH HAZARDS DETERMINATION CF HAOCN EXHAL*TICL N FBCC URANIUM MlNE^Sa) (IN GERMAN» O CEB RACON-EXhALACE T ICN ALS AU - ALEXANDCP, D.R« BAuMATEKl*L1 EN. OR - COLORADO STATE UNIV.i FCRT COLL INS

442 RF - L0523: 74-152011 RE L05L0522 1U : 74-14621 1 TI - NATURAL RADIOACTIVITY IN THE BIOSPHERE ANC FOODSTUFFS. ( T I ESTIMATES OF M ICRCCUS 1 E-D A YS RESIDENCE Ci»E DCSL" T AbULATED DATA . 1 eQ^;rvALe^T. AND ivFo/sue •/ FCP. TI-CBI 2 22 IN MAN US IN AU - CCMAR, C«L.; RUST, J.h. A MANMILLARY MODEL. ANON. AU BERNARD. S • «3 . (CAK RIDGE NATIONAL LAe., TN ). PU - TOXICANTS OCCURRING NATURALLY |N FOODS. WASHINGTON, ÛC. PU BULL. MATH. tilGL. (1973). V. 35 P. 129-147. NAT IONAL ACADEMY OF SCIENCES. I 973. P. 88*105. KE BIOLOGICAL MODELS! BCDt; Ol S TR I BUT I cr* ï ocse ecoiVALENT S : KF - ATMOSPHF.R ic PRECIPITAIICNS: BIOSPHERE; CANADA; CARBON IA; EXCRETICN; MAN; RADIATICN OOSES; ^AQIC NUCL IDE X INETICS; SKELETCK; ThGRIUW CCSMIC OAOIATICN; ORIKKtNG WATER; FALLCUT; FOOD ; HUMAN RAOIUAOI_ H . _224_ ; HAOIUH 228; SINGLE INTAKE; POPULATIONS: ISOTOPE RATIC; NATURAL RADIOACTIVITY; 220; THORI POTASSIUM 40 : PAO T *TICN OCSES; RADIATION ^•A^AROS : RAOIATION MONITCRING; H*O:CECOLCGICAL CCNCENTBATICN; RADIUM 22E; RA0ON 220; HOCKS: SCILS; THORIUM 232; TRIT LUM; TROPOSPHERE ; USA

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4 9b 497 L04I6: 73-075509 RE DETERMINATION OF LCW-LEVEL AMCUNTS OF 229TH IN HUMAN TI LUNÛ CANCER 1N0UCED IN SATS PT THE INHALATlCf CF CAOCN. FUOLOGIC*!- MATERIALS BY ELECTROSTATIC COLLECT ION OF DEC* COMPARISON ITH ThE hi STCLCGIC Al_ ASPECTS CF I-UHAN PRODUCTS CF 220RN. CANCERS. AU KUCHTA* Q*R.Ï SESXID* N.J. JR. ( IN FRENCH) CANCEL eRCKCHO-PgLXCNAIKE EXPER I»£«1H OU OR ARGONNE NATIONAL L*B. « ILL. (USA). 044BO00 RAT PAR INHA LATION DE BAOCN. CCMPifiAlsCN AVEC LES ASPECTS NU L 7960(PT.2», HI STOLQGI0UE S OES CANCEF-S HUMAINS. AN PERBAUD • R » ; ChAMEAuu. j.; LAFUMA, j. ; *A£îE. f.. ; CHRETIEN, J. (CEA, 87 - GAZES (FRANCE1. CIV. MINIERE DE LA CR0U21LLE CEA CENTFE O'ETUDES NUCLEAIRES OE FCHEHÏ- AUX-ROSES. 9 IFRANCEI. CEPT. OE PROTECTICN: CENTRE HOSPITAL1ER LNIVERS I TA IPE . g« - CRETEIL (FRANCE)). 155«000; 12 »ioo; ")looi7<; J. FM. "EO.CHIP. THCBAC. (JAN 1S721, (NC.I1 P. ?<-•!. dOONCMIJ CAO CINCGENESIS: INHALATICN; INTERNAL IRK AO I AT IQN LCCAL KA01AT1CN EffECTSi UM.Î; NECPLA5»S! RAOCN; PATS 509 509 HE - L0*0/: 73-050940 RE - LO4O6: 72-04224*; fi - LATE EFFECTS ON nONË wARROW AFTER INTRAVASAL APPLICATION Tl - RAOIAT1CN UQSE-TlME RtLATlCNS FOB INClCT IC N CF CF TMODOTPAST. OSTEOSAPCCMA I h MICE ANC CCGS

510 51 1 L0405: 72-0459 IB RÉ" - L04J5: 72-045607 STUDIES OF THÇ ELlM|KATlON R*TE *N0 THÉ RAOIATION TI - THORIUM DAUGHTERS IN THE SPLEEN CF A IHCRCTRAST CASE* EXPOSURE FOLLOWING 1NGESTICN OF 222RN «TCH WATER. AU - LUCAS. H.F. JR.; MARK.UK. F.: MAY. M. IAPGCNNE NATIONAL SUOMELA. M.; KAHLOS, T-. (INSTITUTE OF RADIATION PHYSICS* LA0., ILL. (USA)): MACOCKALO. N.S.* SWEENEY. J, 04*8000 HELSINKI (FINLAND))• 3259000 PU - HEALTH PHYS. (CCT 1972). V, 23(41 P. 57S-576. HEALTH PHYS. (NOV IS72». V. 23(5) P. 641-652. NC - efllEF TECHNICAL NCTE. BIOLOGICAL HALF-LIFE; DAUGHTER PRODUCTS; DR INK ING WATER; KE - ACTINIUM 228; eiSMuTH 2l2; DAUGHTER PBCCLCTS; CECAY; EXCRETION; INGEST ICN; MAN; MATHEMATICAL MODELS; MAXIMUM OOGS; MAN: RABBITS; RAOIÛNUCLIOEÎ KINETICS; £«DIUM 224; PERMISSIBLE Dose: RACIATION DOSES; RAOIONUCLIOE KINETICS; RADIUM 22e; RATS: SPLEEN: SPLENECTCMY; THALLIUM zoe; RADON 222: STOMACH; fct-CLE-eOOY CO/NTfRS THORIUM 232; THCRGTRAST! TIME CEPESOEKCE

512 513 L0404: 72-0"3lC2 RE - L0402: ?2-Qje?<4 LATE EFFECT^ IN BONE WARRO» AFTER INTRAVASAL Tl - ON RETENTION OF RADIOACTIVE LAdELLEO AefiCSCL PAPTlCLES C ADMINISTRATIHJ OF THCCCTRAST. DIFFERENT KINDS IN THE fU*AK RESPlf-ATCfiV TRACT. (IN GERMAN). SPAET5CHAE0EN DES KN0CHENMARK5 NACH (IN GERMAN). ZUR AeSCHEIOLKG R*OICAKTtV KAfiKIEPTER INTRAVASALE» TMOPOTfiA STANWENDUNG• AEROSOLPARTIKEL UN T EfiSCf-1 EOL IC H£ R BE SCHAF F ENhE I T I" KAICK. G. VAN (DEUTSOES KfiEQSF CPSCHUNGSZENTRUM » MENSCHLICHEK ATEMTCAKT. MEI DELBERG (F.R. GERMANY). 1NST» FUER NUKLEARMEOIZlN); AU - RE1TER* R. ; CAR NUT»-, • . i POETZL» K. ( FfiALNMOFEP- DOINGS. P. (HEIDELGECG UN IV. (F.R. GERMANY). LU0OLF- GESELLSCHAFT 2UR FCEPOEPUhG OEB *NGE*ANCTEK FCRSCHUNG E. KREHL-KLINIK). 21532Ï0; 9200245 V. , GARM1SCH-PARTENK1RCHEN (F.P. GERMANY). PhYSIKAL ISCh- GESELLSCHAFT FUER NUCLEAWMEO1? !N E.V.. MANCVgH (F.0. BICKLIMATISCHE FOfiSCt-UNCSSTELLE). 25te000 GERMANY). 9200243 PU - ATOMKERNENERGIE• (L472)* V. 20

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622 522 (CCNTINUEOI L0312: 72-03**55 LIVER; LUNGS; MAN; NEOPLASMS; PATIENTS; KACIATICN CCSES; RAOIATION DOSE IN DIFFEREN T ORGANS OF THOROTHAST RADIOACTIVITY; RAOIONUCLICE «INtTKS: RACCN 22 0 ; PATIENTS. RETENTICN; SKELETCN; THCPCTCAST, »HCLE-tJCCY CCUNTEPbl MuTH, H.; EOELMANN* L*« GR ILLMAIER. ft,.; KUNKEL. C: WHOLE-BCOY COUNTING: CMLGHTEK PRCCLCTS; DELAYED ^ACIATICN ORERMâUSEN. F. . IUN1VEPS1TAET DES SAARLANOES. HOMOURG/SAAR EFFECTS: RABBI TS; BADIATICN INJURIES; t-ei ICULCENOCTHEL IAL (F.R. GERMANY». INST. CuER eiOPHYSIK)I HERZFELD* U. < SYSTEM; THORIUM 222; TIME DEPENDENCE HEIDELBERG UNIV. (F.P. GER tCESELLSCHAFT FUEB STBAHLE MNYM; HEYOER . J.; *ER NE R , E> FRANKFURT AM MAIN (F .C . GE N- UNO UMkELTFORSCHUNG M.H.H.I OOEOLER, H.D. (FREtE LNIV, MANY)). KAUL. A,; KOf;PPE* P.* 6509 7 00; 2Q680 0O; 9200007; BEfiL IN (F.R, GFRMANY t). INTERNATIONAL ATOMIC EKERG 2573000 WORLD HEALTH ORGANIZATION, AGENCY, VIENNA (AUSTOJA); 694*000 GENEVA (SWITZERLAND». .12 9 4 0001 I *F A-SM-- |'iO/2 7, ASSESSMENT OF RADIOACTIVE CONT»»1KAI ICN PROCEED INGS OF A SYMCCStU CS ASSESSMENT OQGAN AND FÎODY RUROENS, Q GANl7FC OY Tut IAEA ANC THE *^C ANO HfLO IN STCCKHCL*. 22- 26 NOvEMUER iq ( . Vtt'NNA. ME* . 14 72. D. 45 7-*ft7. PRCEM NGS SEBIES. S YMDOSI UM an i, «SF SS"EN T OF C*O [CACTI VET OP(jAN Avo BC •tUUOENS. STOCKHOLM. S»PCEN . J? NCV ! 571, CAWCIM^As l ts: r«H»L«ncM LEUK^-IAJ 52* RE - C0312: 72-03A«»S RE - L0212: 72-0***42 Tl - MEASUREMENT OF LEAO-210 (ffl-O) IN THE UR1NP OF PEPSCNS Tl - CLEARANCE OF THCRIUM-^22 ANO DAUGHTERS Ffic* THE bLCGD. WITH «AD1U* OURDENS INC ASSESSMENT OF ITS LONG-TEPM AU - KAUL* A. (FRE1E UNIV. eERLIN IF.S. CERHHYH; t-EYOEfi. J EUCRETION RATE FOR LEAO-ZIO. (GESECLSCHAFT FUEB S1"AHLEN- UNO U»»£l. IF Ch SCHUNG X.G.H. AU - KHANOEKAR. R.N.; «FYEKS. C.; OULClNC. J.: KCCHt G.F. ( FRANKFURT tv » AIN (F.R. GERMANYI1. 2E70CCC; Ç2C0CC7 CI'NTRE O» ETUOË OE L»ENEKG1E NUCLCAIPE. MDL trtÊLGIUMII. OM - INTERNAT I CNAt. ATC^IC ENERGY AGENCY, vlt*** (AUSTW1A1; 1Ï71000 WORLD HEALTH 0RGANWAT1CN, GENEVA ( s» M i Bf- L AND ) . 329A00 -Jfl - I NT ERNAT ÎCNAL ATOMIC ENERGY AGENCY, VIENNA {AUSTRIA); 696A000 • ORLO HEALTH ORGAN IZATICN. GENEVA 1S"ITZEHLANOI. 329*000; NO - IAEA-SM--150/25. 693*000 PU - ASSESSMENT CF BAOICACTLVE CON T AM I R, AT 1C N IN «AN. NU - IAFA-SM—150/2. PROCEEDINGS CF A SYMPOSIUM ON ASSESSMENT CF RADIOACTIVE OU - ASSESSMENT OF RADLCACTIVE CONTAM INATICN IN MAN. ORGAN AND SCOT BURDENS, CRGAN12E0 BY TT-E IAEA ANC T*E » PROCEEDINGS OF A SVMPCSIUM ON ASSESSMENT CF RADIOACTIVE ANO HELO IN STCCKHCL", 22-26 NCVCMQEP IÇ71. VIENNA. IAE ÇRGAN ANO ACOV PUBOENS. ORGANIZEC 8V THE IAEA ANO THE WHO 1972. P. 46Ï-

525 S26 OE - L03I2: 72-0J««38 RE - L0312: 72-03AA33 TL - EFFECTS CF LONG-TERM THCP-OTRAST EXPOSURE. Tl - EVALUATION CF THE BUR0ÊN CF THE 1SCTCFES 210P6. 21001 ANC AU - JANOVER, M.L.; «1ETTINEN, O.S.; FLVNN, M.J. 210PO IN TKE ORGANS CF RATS CONTAMINATED THROUGH Tf-E PU - RADIOLOGY. (APR 1972). V. 103(11 P. 13-20. RESPlRATCRr TRACT klTH KACCN ANO ITS DAUGHTER PRCOUCTS, KE - CAOCINOGENESIS; OELAYEO RADIATION EFFECTS; INJECTION; (IN FRENCHI. EVALUATION OE 210PBc 210BI £T 210P0 PRESENTS LEUKEMOGENESIS; MAN; PATHOLOGICAL CHANGES; RAOIATION DANS LES ORGANES CE PATS CCNTAMINES PAF VC1E RESPIRATOIRE INJURIES; THORCTRAST; TIME DEPENDENCE AVEC LE RAOON ET SES DESCENDANTS RAOtCACT I FS . AU - FURN1CA. G.; TCAOEP, M. CR - INTERNATIONAL ATCMIC ENCCGY AGENCY, VIENNA (AUSTRIA); • ORLO HEALTH ORGANIZATION. GENtVA I Sa11ZERLAND I . 32VAOOO: 699*000 UU - IAEA-SM--I50/I5. PU - ASSESSMENT OF RADIOACTIVE CONTAMINATION IN MAN. PROCEEDINGS CF A SYMPOSIUM ON ASSESSMENT CF BAO1OAC T 1VE. 0RSAN «NO BCOY euCOCNS. CBGANWED eY THE IAEA AND ThE «HC AND HELO IN STCCKHCLM, 22-26 NCVSMeEP 1WI. VIENNA. IAEA. 1972. P. SA3-S51. PNCCEEOINGS SERIES. CC - SYMPOSIUM ON ASSESSMENT CF HA010ACTIVE CfcGAN ANO BCCY BURDENS. STOCKHOLM, S«ECEN. 22 NCV 1*71. KE - BISMUTH 210; CCNTAM1NATICN: CAUGHTEH PfiCCUCTS» CXCBETION; INHALATION; KlONEYSi LEAD 210; LIVES; LUNGS; PCLCN1U" 2io; RADIOACTIVITY; RAOCN; GATS: CESPISATCBY SYSitx: RETENTION; SKELETCN; URINE

53» 535 L0301! 7Î-026AJ3 RE - L030B! 72-023571 TMOOIUM-2JB CONTENT IN TOBACCO ANO THE HUMAN BOOR. Tl - COMMENT: HAOlCNuCLInt CARC1NCGENES1S ANC SINUS (IN RUSSIAN). 0 SODEHZHANII TORIYA-228 V TABAKE I CARCINOMA. ORGANIÎME CHELOVETCA. AU - RUBIN, p. PETUSHKOV. A.A.I ZELTSEB, M.H.; MEOVEOOVSKIJ , A.P. I PU - J. AMER. MEO. ASS. (17 JAN 15721. V. 21 % 13 I P. J5«-355. AKADEMIVA MFOITSIN5KIKM NAUK SSSR. «OSCO». INST. GIG1ENY KE - ALPHA PARTICLES; BETA PARTICLES! 6CN£ TISSUES", TRUOA I PROFESSIONAL'NVKM IAB0LEVAN IJI. 0153000 CARCINCGENESIS ; OALGMTER PPCCUCTS; OÉLAYEC RACIAT1CN PU GIG. SANIT. (AOR 1972). INC.4) P. 113-I I «. EFFECTS; OCSE-S£SPCNEE CEI AT IONS" 1 PS : EF1THELIU»; "AN; NO FOR FNGLISH TQANSLATICN SEE THE JOURNAL HYG. SANIT. RADIATION DOSES*. R AO IC ISOTCPES :