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Maeck, W.J.; Emel, W.A.; Delmore, J.E.
Dosimetry methods for fuels, cladding, and structural materials1977
Dosimetry methods for fuels, cladding, and structural materials1977
AbstractAbstract
[en] The INEL fission yield measurement program and the current status of the results are reviewed. Fast reactor fission yields for 233U, 235U, 238U, 239Pu, 241Pu, and 237Np obtained for samples irradiated in Row-8 of EBR-II have been reported. The neutron spectrum associated with the reported yields has been reported. Measurement of fast reactor fission yields for 240Pu, 242Pu, and 241Am is in progress. To supplement these data, and to provide additional correlation points relative to the effect of neutron energy on fission yields, a series of samples previously irradiated in the axial blanket and Row-2 to 4 of EBR-II has been obtained for analysis. Future efforts relative to recommending and prooftesting methods for the analysis of burnup for FBR fuels are discussed
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Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 1267-1278; 1977; p. 1267-1278; 2. ASTM-EURATOM symposium on reactor dosimetry: dosimetry methods for fuels, cladding and structural materials; Palo Alto, CA, USA; 2 - 7 Oct 1977
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Report
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Conference
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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, AMERICIUM ISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BREEDER REACTORS, DOSIMETRY, EPITHERMAL REACTORS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FAST REACTORS, FBR TYPE REACTORS, HEAVY NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIQUID METAL COOLED REACTORS, MINUTES LIVING RADIOISOTOPES, NEPTUNIUM ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, PLUTONIUM ISOTOPES, RADIOACTIVE MATERIALS, RADIOISOTOPES, REACTORS, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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