Published 1989 | Version v1
Miscellaneous Metadata-only

Results of computerized simulation for depressurization

Creators

  • 1. Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, SP (Brazil). Dept. de Tecnologia de Reatores

Description

The CANON experience simulation of depressurization due to a loss of primary coolant accident im PWR reactors, by TRAC/PF1, RELAP4/MOD5, RELAP5/MOD1, TRAC/PD2 and RELAP4/MOD3 is presented. The results obtained these codes are evaluated comparing with values obtained experimentally. (M.C.K.)

Availability note (English)

Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.

Abstract (Portuguese)

Apresenta-se a simulacao da experiencia CANON de despressurizacao devido a um acidente por perda de refrigerante primario em reatores PWR, Atraves dos codigos: TRAC/PF1, RELAP4/MODS5, RELAP5/MOD1 TRAC/PD2 e RELAP4/MOD3. Os resultados obtidos por estes codigos sao avaliados comparando-os com os valores obtidos experimentalmente. (M.C.K.)

Additional details

Additional titles

Original title (Portuguese)
Resultado da simulacao de despressurizacao atraves de codigos computacionais

Publishing Information

Imprint Title
Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 3
Imprint Pagination
544 p.
Journal Page Range
p. 11-38.

Conference

Title
7. National Meeting of Reactor Physics and Thermohydraulic.
Dates
26-28 Apr 1989.
Place
Recife, PE (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
20061724
Subject category
S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; EVALUATED DATA; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; T CODES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 7. Encontro Nacional de Fisica de Reatores e Termohidraulica. v. 3.