Published 2010 | Version v1
Book Metadata-only

Verification of the plant dynamics analytical code CERES; Comparison with EBR-II tests

Creators

  • 1. Central Research Inst. of Electric Power Industry (CRIEPI), 2-11-1 Iwado Kita, Komae City, Tokyo 201-8511 (Japan)
  • 2. Argonne National Laboratory, 9700 S Cass Ave., Argonne, IL 60439 (United States)

Description

CERES is a plant dynamics simulation code for LMRs (Liquid Metal Reactors) developed by the CRIEPI (Central Research Inst. of Electric Power Industry). It differs from general similar codes in having a multi-dimensional plenum model. The verification that uses the reactor trip test data of the prototype fast breeder reactor 'Monju' has been executed, and the analytical capability of the CERES under forced circulation was confirmed. The verification results of the natural circulation condition are described in this paper. (authors)

Part of:
Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP '10

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
978-89448-081-2
Imprint Title
Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP '10
Imprint Pagination
2284 p.
Journal Page Range
p. 659-666

Conference

Title
2010 International Congress on Advances in Nuclear Power Plants
Acronym
ICAPP '10
Dates
13-17 Jun 2010
Place
San Diego, CA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
42099954
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
C CODES; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; EBR-2 REACTOR; EXCURSIONS; EXPERIMENTAL DATA; MONJU REACTOR; NATURAL CONVECTION; REACTOR KINETICS; VERIFICATION
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; CONVECTION; DATA; ENERGY TRANSFER; EPITHERMAL REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; INFORMATION; KINETICS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MASS TRANSFER; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SODIUM COOLED REACTORS

Optional Information

Notes
8 refs.