Published 1990 | Version v1
Book

Benchmark tests of JENDL-3 for thermal and fast reactors

  • 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

Part of:
The physics of reactors: operation, design and computation. Volume 3

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

Optional Information