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Andoh, Masaki; Iijima, Susumu; Iwai, Takehiko
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
AbstractAbstract
[en] As a research on FBR with new types of fuel, a series of experiments on a nitride fuel fast reactor was carried out at Fast Critical Assembly (FCA). The criticality data measured in the FCA XIX-2 core was applied to the adjustment of the nuclear data library and the calculation accuracy of the adjusted library for criticality of a 1000 MWe nitride fuel FBR core was evaluated. By reflecting the present measurement on the unified cross-section set, the calculation accuracy on the criticality of the nitride fuel FBR core was improved by 0.1%. It was found that the uncertainty of the capture cross section of 14N at the energy range of MeV affected the calculation accuracy. (author)
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Source
Mar 2000; 53 p; 15 refs., 15 tabs., 7 figs.
Record Type
Report
Literature Type
Numerical Data
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CROSS SECTIONS, DATA, ENERGY SOURCES, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FUELS, INFORMATION, ISOTOPES, LIGHT NUCLEI, MATERIALS, NITROGEN ISOTOPES, NUCLEAR FUELS, NUCLEI, NUMERICAL DATA, ODD-ODD NUCLEI, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID FUELS, STABLE ISOTOPES, ZERO POWER REACTORS
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