ML19250B431
| ML19250B431 | |
| Person / Time | |
|---|---|
| Issue date: | 10/01/1979 |
| From: | Foulke J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Swanberg F NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 7910310051 | |
| Download: ML19250B431 (5) | |
Text
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na arG UNITED STATES Y.,,,,,[
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WASHINGTON, D. C. 20555
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OCT 1 1979
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MEMORANDUM FOR:
Frank Swanberg, Chief Environmental Effects Research Branch Division of Safeguards, Fuel Cycle and Environmental Research 1
FROM:
Judith D. Foulke Environmental Effects Research Branch Division of Safeguards, Fuel Cycle and Environmental Research
SUBJECT:
PROGRAM REVIEW 0F PROJECTS AT THE INHALATION T0XICOLOGY RESEARCH INSTITUTE On August 21, 1979, a research review group meeting was held at the Inhalation Toxicology Research Institute (ITRI) in Albuquerque, New Mexico to review the progress of the two NRC-sponsored studies.
e Radiation Dose Estimates and Hazard Evaluation for Inhaled Airborne Radionuclides e Biological Characterization of Radiation Exposure and Dose Estimates for Inhaled Uranium Milling Effluents NRC attendees are listed in Enclosure 1 and ITRI staff participants are listed in Enclosure 2, which includes the agenda for the program.
Dr. Jim Mewhinney, project coordinator for the mixed oxide study, presented a brief overview of " Radiation Dose Estimates and Hazard Evaluations for Inhaled Airborne Radionuclides." Dr. Frank Eidson presented infomation on the physical /
chemical characterization of the three mixed oxide and one pure plutonium oxide samples. He noted that infrared analysis showed that water and carbon dioxide are adsorbed on the surface of respirable particles causing them to become partly hydrolized.
ESCA analyses showed that surface uranium is oxidized to U0 -
3 Dr. Eidson also reported on in vitro dissolution studies of the aerosol materials.
In both serum simulant and O'TM hcl plutonium dissolved much more rapidly from the HEDL 1750*C mixed oxide, which had been detemined from X-ray diffraction itudies, to be a solid solution, than from the other mixed oxides of uranium and plutonium. The two component dissolution curves were ascribed to the presence of a surface layer which differs from the interior of the particles.
Dr. Ray Guilmette discussed the problem encountered in perfoming uranium analyses on biological samples. He described an improved fluorometric procedure involving extraction with TOP 0 for quantitative recovery of 20% of the sample, use of a fusion burner for multiple samples to reduce variation among samples below 2%,
and modification of the flurometer to increase the sensitivity from 1.Ong to 0.2ng.
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F. Swanberg OCT 1 1973 Mr. Andy Stanley presented the dose pattern results for the 750'C mixed oxide material in rats, dogs, and monkeys for plutonium. He described the method of determining the initial lung burden and presented excretion curves for feces and urine. To date the results show that most of the Pu (and Am daughter) leaves the lung via mechanical clearance; there is very little in vivo dissolution.
- with rats being Monkeys and rats clect Pu from their lungs much faster than dogs somevhat faster than monkeys.
Dogs accumulate more Pu in their tracheobronchial lymph nodes than monkey,s or rats. Smail amounts of Pu am found in the liver and skeleton of all three species.
Dr. Jim Mewhinney presented a comparison of the radiation dose patterns at 1.5 years in dogs and monkeys for the pure Pu0, the 750*C Pu02-UO, and the 1750*C 2
2 (PuV)0.96 materials.
In dogs 74-95% of the sacrifice bodybu,rden was in the,
1 lung; most of the remainder was in the tracheobronchial lymph nodes.
In monkeys 91-99% of the sacrifice bodyburden was in the lung with most of the remainder in the tracheobronchial lymph nodes. In both species the material that least translocated was the 750*C (Pu0 -UO2).
2 Dr. Fletcher Hahn discussed the determination of the local distribution of Pu-239 in the lungs of dogs and monkeys up to 1.5 years.
Results show the plutonium concentration are similar in alveoli near the pleura, alveoli near the bronchioles, and alveolar parenchyma. He also presented the biological effects, namely in-flammation of the lung and lung cancer, observed to date. Of 43 animals with lung lesions, 27 have been examined.
Preliminary dose-effect estimates showed squamous cell tumors at average doses of 9200 rads, adenocarinomas at 2800 rads, and nesotheliomas at 3300 r-is.
Mr. Bill Griffith and Dr. Jiu Mewhinney presented proposed dose-response studies for inhaled mixed oxide acersols in rats. The materials to be studied are the 850*C Pu02 and the 1750 C iPu, U) 0.96 aa""i$.
Projected lung doses are 1
25, 125, and 625 rads.
Dr. Frank Eidson, proact coordinator for the yellowcake study, presented an overview of "Biologie A Characterization of Radiation Exposure and Dose Estimates for Inhaled Uran 6 Mi>iing Effluents." He noted that he has contacted five mills in New Mexico and would be visiting one by the end of the month. Previous physical /
chemical characterization studies on yellowcake samples provided by NRC were reviewed.
Dissolutich rates in serum simulant compared well with available human data.
Dr. Ed Damon presented proposed short-term and long-tenn animal studies similar to those conducted with mixed oxides. Yellowcake materials already on hand would be used to inhalation exposures in rats with sacrifice scheduled from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 180 days. Long-tena (2 years) inhalation studies in rats and dogs would be conducted with yellowcake materials chosen for unique characteristics following field sampling.
At the request of NRC (K. Alexander, OHSB) further in vitro solubility studies are being conducted to resolve conflicting results found by Nancy Dennis of the University of Pittsburgh. ITRI's hypothesis is that the presence of phosphate ions in her serum simulant caused formation of insoluble NH UO2P0, which made 4
4 it appear that none (less than 1%) of tha uranium dissolved from the yellowcake.
ITRI will repeat Dennis' work with and without phosphate.
eb. % h udith D. Foulke 7nq Environmental Effects Research Branch Division of Safeguards, Fuel Cycle and Enclosures : As Stated Environmental Research
ENCLOSURE 1 NRC ATTENDEES Judith D. Foulke RES/ SAFER R. B. Neel NMSS/FCTA Frank Swanberg, Jr.
RES/ SAFER
}
Steven Whitfield OSD/RHSB 883 310
REVISED AGENDA NRC SITE VISIT August 21, 1979 I.
We l come ---------------------------------------- --------D r. Rog e r licC l e l l a n II.
Introduction-------------------------------------------Dr.
Bruce Boecte*
III.
Project 1
" Radiation Dose Estimates and Hazard Evaluations for Inhaled Airborne Radionuclides"-
A.
Physical Chemical Characterization of Mixed 0xide Nuclear Fuel Material s--------------------Dr. Frank Eidson B.
In_ Vitro Dissolution Properties of Mixed Oxide Nuclear Fuel Ma teri al s--------------------Dr. Frank Eidson C.
Fluorometric Analytical Procedure for Uranium in Biological Matrices------------------Dr.
Ray Guilmette Comparative Radiation Dose Pattern Studies oI w D.
Involving Inhalation Exposure to liixed 0xide Aerosols 1.
750'C Heat-Treated Pu0 -U0 ------------------Mr. Andy Stanley 2
2 2.
Comparison of 850 C Pu0, 750*C Pu0 -UO2 2
2 and 1750 C (Pu,U)01. 9 6---------------------Dr. J i m Mewhi nney 3.
Future Modeling Activities-------------------Dr. Jim Mewhinney 239 E.
Measurements cf Local Distribution of pu Within the Lungs of Dogs and Monkeys------------Dr. Fletcher Hahn F.
Comparative Study of Dose-Response Relationships for Inhaled Mixed Actinide Oxide Aerosols 1.
Observed Biological Effects------------------Dr. Fletcher Hahn 2.
Experimental Design Consit'erations-----------Mr. Bill Griffith 3.
Future Experimental Plans--------------------Dr. Jim Mewhinney G.
Project Summary-------------------------------
--Dr. Jim Mewhinney IV.
Project 2
" Biological Characterization of Radiation Exposure and Doss Estimates for Inhaled 88-)
3ll Uranium Milling Effluents" A.
Field Collection---------------------------------)
)Dr. Frank % s_on B.
Physi cal Chemical Characterization---------------)
C.
Dose Pattern Studies---------------------------------)
)-Dr. Ed Damon D.
Modeling Activities--------------------------------.-)
E.
Applications-----------------------------------------
Dr. Frank Eidsen 1.
Bioassa'y 2.
Hazard Evaluations V.
General Discussion
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883 312
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