Published 1989 | Version v1
Miscellaneous Metadata-only

Use of RELAP4/MOD3 and RELAP/MOD5 computer codes for simulating CANON experience

Creators

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

Description

The results obtained by RELAP4/MOD3 and RELAP4/MOD5 computer codes for simulating depressurization phase during a loss of primary coolant accident in PWR type reactors, from CANON experience, are presented. (M.C.K.)

Availability note (English)

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

Abstract (Portuguese)

Apresentam-se os resultados obtidos pelos codigos RELAP4/MOD3 e RELAP4/MOD5 da simulacao de despressurizacao devido a um acidente por perda de refrigerante primario em reatores PWR, da experiencia CANON. (M.C.K.)

Additional details

Additional titles

Original title (Portuguese)
Utilizacao dos codigos RELAP4/MOD3 e RELAP4/MOD5 para simulacao da experiencia CANON

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. 321-397.

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
20061729
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
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; EVALUATED DATA; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; 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.