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Mullins, L.J.; Foxx, C.L.
Los Alamos National Lab., NM (USA)1982
Los Alamos National Lab., NM (USA)1982
AbstractAbstract
[en] The process for reducing 700 g 239PuO2 to metal is a standard procedure at Los Alamos National Laboratory. This process is based on research for reducing 200 g 238PuO2 to metal. This report describes in detail the experiments and development of the 200-g process. The procedure uses calcium metal as the reducing agent in a molten CaCl2 solvent system. The process to convert impure plutonia to high-purity metal by oxide reduction followed by electrorefining is also described
Primary Subject
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Feb 1982; 19 p; Available from NTIS., PC A02/MF A01 as DE82009713
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Report
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Best, R.E.; Ridihalgh, J.L.
Proceedings of the 4th international symposium on packaging and transportation of radioactive materials1974
Proceedings of the 4th international symposium on packaging and transportation of radioactive materials1974
AbstractAbstract
No abstract available
Primary Subject
Source
Union Carbide Corp., Oak Ridge, Tenn. (USA). Nuclear Div; p. 873-882; 1974; 4. international symposium on packaging and transportation of radioactive materials; Miami Beach, Florida, USA; 22 Sep 1974
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Report
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Oshima, H.; Kubo, M.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
AbstractAbstract
No abstract available
Primary Subject
Source
Oak Ridge National Lab., TN (USA); p. D.I.9-D.I.10; 1983; p. D.I.9-D.I.10; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A21/MF A01; 1 as DE83012390
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Report
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AbstractAbstract
[en] Letter-to-the-editor
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Journal Article
Journal
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Pechin, W.H.; Bradley, R.A.; Sease, J.D.
USAEC, Washington, D.C.1974
USAEC, Washington, D.C.1974
AbstractAbstract
No abstract available
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Source
17 Dec 1974; 7 p; CA PATENT DOCUMENT 959252; Available from Commissioner of Patents, Ottawa; Filed 4 May 1971. Priority USA 8 Jun 1970 (44,572). 2 claims. Available from Commissioner of Patents, Ottawa.
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Patent
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Nolibe, D.; Masse, R.; Fritsch, P.; Lafuma, J.
Biological and environmental effects of low-level radiation1976
Biological and environmental effects of low-level radiation1976
AbstractAbstract
[en] Pulmonary fragments from control rats (Wistar) of varying age and contaminated with PuO2 were grafted in an immunodeficient medium onto mice or histocompatible rats. In both cases the authors observed lesions presenting the histological characteristics of pulmonary cancer in rats; proliferation, however, remained discrete. After grafting on the athymic mice, the lungs of the control animals exhibited a percentage of tumoral-type differentiations which increased with age. in the contaminated rats, for an initial pulmonary burden of 10 nCi and cumulative doses of between 6X108 and 38X109 α/g of lung, the grafts showed a clear-cut increase in lesions of this type. Their frequency increased with the total dose delivered. Conversely, if the dose delivered during a three-month period varied from 2X108 to 50X109 α/g of lung, the maximum proliferation was observed at the lowest doses. Furthermore, the histological nature of the proliferations varied with the dose delivered. This transplantation technique would appear to show the existence of lesions which are not yet overt and which are a consequence either of ageing or of α-irration. The authors discuss the meaning of these lesions and the immunological component of the phenonmenon. (author)
Original Title
Greffe chez la souris athymique de tissu pulmonaire de rat contamine
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); World Health Organization, Geneva (Switzerland); Proceedings series; v. 2 p.95-107; ISBN 92-0-010176-3;
; 1976; IAEA; Vienna; Symposium on biological effects of low-level radiation pertinent to protection of man and his environment; Chicago, Ill., USA; 3 Nov 1975; IAEA-SM--202/403

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Book
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Bronson, M C; Zundelevich, Y.
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States). Funding organisation: USDOE (United States)1998
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States). Funding organisation: USDOE (United States)1998
AbstractAbstract
[en] Options for plutonium disposition require PuO2 that can be used as feed material for mixed oxide (MOX) reactor fuel pellets, or glass and ceramic immobilization forms (cf. Federal Register Doc. 97-1355, Vol. 62, No. 13, January 2 1,1997). As part of a DOE-sponsored demonstration known as the Advanced Recovery and Integrated Extraction System (ARIES), conversion of plutonium to oxide by the Hydride/Oxidation (HYDOX) process will be used, along with other supporting technologies, to recover plutonium from the cores or *number sign 34;pits'' of nuclear weapons that have been determined to be surplus to national defense needs. This demonstration will be performed jointly by the Los Alamos and the Lawrence Livermore National Laboratories at the Los Alamos Plutonium Facility. The pyrochemical methods employed by HYDOX offer a simple and reliable process to recover plutonium in oxide form from various sources. This process will: Separate plutonium from other nuclear and non-nuclear materials, Convert massive metallic shapes into fine oxide particles, Produce oxide directly acceptable for MOX fuel fabrication, and Produce no solid or liquid waste. The paper describes the reactor module and operational sequences, provides up-to-date experimental results, identifies rate-controlling factors, and discusses their impact on the reactor design
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Source
19 Jun 1998; 1 Megabytes; 3. Topical Meeting of the American Nuclear Society; Charleston, SC (United States); 8-11 Sep 1998; CONTRACT W-7405-ENG-48; Available from OSTI; NTIS; URL:http://www.llnl.gov/tid/lof/documents/pdf/234740.pdf; US Govt. Printing Office Dep; GA0102011
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Oshima, H.; Kubo, M.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
AbstractAbstract
[en] The packaging has been developed as a packaging for plutonium oxide to be recovered from light water reactor spent fuel and is designed for easy handling within a facility. As deformation and shock absorption data for balsa wood, the data obtained from various experiments carried out when developing the packaging were used. With this packaging, it is possible to transport almost all kinds of raw powder materials required to produce fuel as stated under Section 2 not only in the country but also from abroad. The packaging is expected to be frequently used in transporting plutonium oxide powder from England and/or France which are commissioned by domestic power companies to reprocess spent fuel and also in transporting highly enriched uranium oxide which is required at FBR experimental reactors. 14 references, 5 figures, 4 tables
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Oak Ridge National Lab., TN (USA); p. 390-398; Dec 1983; p. 390-398; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A99/MF A01; 1 as TI84006239
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Report
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Arnal, T.; Auchapt, P.; Ferlay, A.; Marchal, P.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
AbstractAbstract
No abstract available
Primary Subject
Source
Oak Ridge National Lab., TN (USA); p. D.I.5-D.I.6; 1983; p. D.I.5-D.I.6; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A21/MF A01; 1 as DE83012390
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Report
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Scott, Bobby R.; Cheng, Yung-Sung; Zhou, Yue; Tokarskaya, Zoya B.; Zhuntova, Galina V.
Lovelace Biomedical and Environmental Research Institute, Albuquerque, NM (United States). Funding organisation: USDOE Office of Environmental Management EM (United States)2001
Lovelace Biomedical and Environmental Research Institute, Albuquerque, NM (United States). Funding organisation: USDOE Office of Environmental Management EM (United States)2001
AbstractAbstract
[en] The main objective of this project is to improve capabilities for evaluating health risks to humans associated with inhaling plutonium (Pu). Two key DOE issues are being addressed: (1) the need to improve capabilities for evaluating plutonium dioxide (PuO2)-associated health risks for DOE workers involved in decommissioning/decontamination (D and D) activities; and (2) the need to improve capabilities for evaluating health risks for public exposures arising from residual PuO2 in soil at remediated (cleaned-up) DOE sites. The scientific goal of this project is to improve capabilities for assessing health risk distributions for DOE workers and the public associated with inhaling Pu. The focus of our work has been on DOE worker and public exposure scenarios related to the Rocky Flats Environmental Technology Site near Denver, Colorado, commonly called Rocky Flats
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1 Jun 2001; [vp.]; FG--07-00ER62511; Available from PURL: https://www.osti.gov/servlets/purl/834690-rIyC1s/native/
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