Published 1990
| Version v1
Book
Benchmark tests of JENDL-3 for thermal and fast reactors
Creators
- 1. Japan Atomic Energy Research Inst., Tokai Ibaraki (Japan)
Description
Continuous efforts have been devoted to the benchmark tests of the Japanese Evaluated Nuclear Data Library, revision 3 (JENDL-3), for a variety of thermal and fast reactors. The benchmark results show generally much adequate prediction of nuclear characteristics in comparison with those obtained by JENDL-2. It is concluded, especially, in the fast reactor bencmarks that space dependences of the ratios of calculation to experiment (C/E) for reaction rate distributions, sodium void reactivity worths and control rod worths are considerably improved by JENDL-3. The prediction of burnup characteristics for PWR spent fuel is satisfactory in comparing that of ORIGEN2
Additional details
Publishing Information
- Publisher
- Societe Francaise pour l'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- The physics of reactors: operation, design and computation. Volume 3
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. I.21-I.32.
Conference
- Title
- Operation, Design and Computation.
- Acronym
- International Conference on the Physics of Reactors
- Dates
- 23-27 Apr 1990.
- Place
- Marseille (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 22012500
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; CONTROL ROD WORTHS; CRITICALITY; FAST REACTORS; MULTIPLICATION FACTORS; NUCLEAR DATA COLLECTIONS; THERMAL REACTORS; VOID COEFFICIENT
- Descriptors DEC
- EPITHERMAL REACTORS; REACTIVITY COEFFICIENTS; REACTORS