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AbstractAbstract
[en] Radionuclides associated with soil particles can be transported to plant surfaces by wind, raindrop splash, animal activities and mechanical disturbance and can contribute to radiation exposure through ingestion by humans or livestock. The quantities of radionuclides ingested with soil particles borne on plant surfaces can be estimated from the mass loadings of soil on plant surfaces (i.e. mg soil per g dry plant mass) and the radionuclide concentrations in soil. However, relatively few estimates of mass loadings are available for either row or pasture crops. Estimates of the concentration of soil on bahia grass, a common pasture species on the sandy soils of the southeastern United States, were obtained using 238Pu as an indicator of the presence of soil on vegetation. The mass loading of soil on live bahia biomass average 9.0 mg g-1, which is similar to that for some row crops grown on the same soils. The mass loading for bahia pasture may be less than that for English pastures but differences in methodologies among studies complicate comparisons. (author)
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CONTRACT DE-AC09-76SROO-819
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AbstractAbstract
[en] This paper describes results of investigations of questions concerning integrity keeping for an ampula containing radionuclide fuel (Pu-238) under conditions of emergency landing in dense layers of the atmosphere and under conditions of fire on launching pad. copyright 1996 American Institute of Physics
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STAIF 96: space technology and applications international forum; Albuquerque, NM (United States); 7-11 Jan 1996; CONF-960109--
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AbstractAbstract
[en] The decay data evaluation results have been presented for three plutonium isotopes: 238Pu, 240Pu, and 242Pu. The evaluated data have been obtained using information published up to 2004
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International conference on nuclear data for science and technology; Santa Fe, NM (United States); 26 Sep - 1 Oct 2004; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
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Ewing, R.I.; Bierman, S.R.
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: USDOE, Washington, DC (United States)1992
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: USDOE, Washington, DC (United States)1992
AbstractAbstract
[en] In this report we will consider how radiation measurements on spent fuel can contribute to verifying the loading of burnup credit casks. Measurements can be used in burnup credit operations to help prevent misloading of fuel that does not meet the minimum specifications for a particular cask design. Passive neutron and gross gamma-ray measurements are proposed as a means of qualifying spent fuel assemblies. Active systems to measure reactivity or fissile content are necessarily more complex and appear to offer no obvious advantage to burnup credit applications over simpler systems. 4 refs., 2 figs
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1992; 8 p; Institute of Nuclear Material Management (INMM) winter meeting; Washington, DC (United States); 15-17 Jan 1992; CONF-920164--1; CONTRACT AC04-76DP00789; AC06-76RL01830; OSTI as DE92006676; NTIS; INIS; US Govt. Printing Office Dep
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Report
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Pustovalov, A.A.; Lazarenko, Y.V.; Shapovalov, V.P.
Proceedings of the 24th intersociety energy conversion engineering conference. Volume 61989
Proceedings of the 24th intersociety energy conversion engineering conference. Volume 61989
AbstractAbstract
[en] The interest shown to the radionuclide electric power sources as explained by a number of their features. The main features are described. The evaluation of a number of commercially produced radionuclides shows that at present Pu238 radionuclide and sometimes Am241 radionuclide are widely applicable in small-size RTG according to their characteristics. The authors describe how Pu238 has been widely used in domestic and foreign production of small-size RTGs. Future applications for Pu238 are discussed
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Anon; Post-deadline papers and index; 2950 p; 1989; p. 2673-2680; IEEE Service Center; Piscataway, NJ (USA); 24. intersociety energy conversion engineering conference; Arlington, VA (USA); 6-11 Aug 1989; CONF-890815--; IEEE Service Center, 445 Hoes Ln., Piscataway, NJ 08854 (USA)
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AbstractAbstract
[en] In the paper, the production procedures and physics basics for "2"3"8Pu are introduced. Irradiation production processes such as design of "2"3"7Np target rod, target rod load capacity of "2"3"7Np and "2'3"8Pu yield of calculation are presented. Furthermore, the post-irradiation technical procedures including chemical separating, purifying, recycling, "2"3"8Pu powder acquirement and heat source fabrication, are also summarized with cautious. (authors)
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5 figs., 2 tabs., 8 refs.
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Journal Article
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Nuclear Power Engineering; ISSN 0258-0926;
; v. 36(2); p. 17-20

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[en] The transfer of 238Pu from the maternal circulation to the developing embryo and fetus was studied in rats and guinea-pigs to provide data for the development of dosimetric models for the human embryo and fetus. Measurements were also made of the 238Pu retention in neonates at birth. For administration at each stage of gestation, and particularly at early stages, transfer of 238Pu to the fetus continued throughout gestation but concentrations decreased due to fetal growth. (author)
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[en] This report concerns an international comparison of measurements of a solution of 238Pu that was carried out by 12 participants in 2001. The report includes the degrees of equivalence. (authors)
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1 ref.
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Metrologia; ISSN 0026-1394;
; v. 55(no.1A); p. 06004.1-06004.32

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Clark, David L., E-mail: dlclark@lanl.gov
Proceedings of the thirteenth DAE-BRNS nuclear and radiochemistry symposium2017
Proceedings of the thirteenth DAE-BRNS nuclear and radiochemistry symposium2017
AbstractAbstract
[en] "2"3"8Pu has found important application in radioisotope power systems - nuclear power systems that derive their energy from the heat produced by spontaneous radioactive decay, as distinguished from nuclear fission. Most radioisotope power systems use "2"3"8Pu as an isotope heat source. An overview of the production, purification, component fabrication, safety testing, actual applications, and disposal of this very important isotope will be presented here
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Mohapatra, M.; Pujari, P.K. (Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai (India)) (eds.); Dash, S. (ed.) (Fuel Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India)); Raskhit, S.K. (ed.) (Product Development Division, Bhabha Atomic Research Centre, Mumbai (India)); Tomar, B.S. (ed.) (Radiochemistry and Isotope Group, Bhabha Atomic Research Centre, Mumbai (India)); Bhabha Atomic Research Centre, Mumbai (India); Indian Association of Nuclear Chemists and Allied Scientists, Mumbai (India); KIIT University, Bhubaneswar (India); 750 p; ISBN 81-8372-080-3;
; 2017; p. 51-52; NUCAR-2017: 13. DAE-BRNS nuclear and radiochemistry symposium; Bhubaneswar (India); 6-10 Feb 2017; 3 refs., 3 figs.

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Lee, Myung Ho; Lee, Chang Woo; Choi, Yong Ho; Kim, Sang Bok; Kim, Sam Rang
Proceedings of the KNS autumn meeting1995
Proceedings of the KNS autumn meeting1995
AbstractAbstract
[en] The cumulative deposition of Pu-238 and Pu-239, 240 by the end of 1994 in undisturbed for the last 40 years, was determined at 9 sites in Korea. The cumulative deposition of Pu-238 and Pu-239 ranged from 0.76 to 3.77 and from 18.42 to 101.84 Bqm-2, respectively. The mean values of the cumulative deposition of Pu-238 and Pu-239, 240 were 2.16 and 54.75 Bqm-2, respectively. These values are close to the value of worldwide fallout. No significant contribution to the cumulative deposition of Pu-238 and Pu-239, 240 originating from the Chernobyl accident was found at any site
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Korean Nuclear Society, Taejon (Korea, Republic of); 1059 p; 1995; p. 893-898; 1995 autumn meeting of the KNS; Seoul (Korea, Republic of); 28 Oct 1995; Available from KNS, Taejon (KR); 9 refs, 1 tab
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