Published 1989
| Version v1
Miscellaneous
Comparison of results obtained by RELAP4/MOD3 and RELAP4/MOD5 in simulating depressurization phase of loss of primary coolant accident in Angra-1 nuclear power plant
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, SP (Brazil)
Description
It's very important to obtain information of certain thermal hydraulic parameters of the Angra 1 Nuclear Power Plant during a Large LOCA in three different points: in the cold leg, in the hot leg between the steam generator and the pump. In this way, these paper describes the results comparison of these accidents with the RELAP4/MOD3 and RELAP4/MOD5 codes with the results in the 'Final Safety Analysis Report' of Angra 1. It was used a 36 control volume model, with 48 junctions between the control volumes, 25 heat exchange structures and 8 valves. The transient analysis were made just during the blowdown phase of the LOCA. (author)
Availability note (English)
Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.Abstract (Portuguese)
Levando-se em consideracao a grande importancia de se obter informacoes com relacao ao comportamento de determinados parametros termohidraulicos da Planta Nuclear de Angra 1, quando sujeita a um Acidente de Perda de Refrigerante Primario por Grande Ruputura - APRPGR em tres pontos distintos do circuito primario, isto e, na perna fria, na perna quente e entre o gerador de vapor e a bomba, realizou-se a partir da simulacao destes acidentes uma comparacao entre os resultados obtidos com os Codigos RELAP4/MOD3 e RELAP4/MOD5 com os resultados fornecidos pelo 'Final Safety Analysis Report' - FSAR de Angra 1. Utilizou-se para isto uma modelagem contendo 36 volumes de controle, 48 juncoes de interligacao dos volumes de controle, 25 estruturas de troca de calor e 8 valvulas. OS transientes analisados compreendem apenas a fase de despressurizacao do APRPGR. (autor)Additional details
Additional titles
- Original title (Portuguese)
- Comparacao dos resultados obtidos com os codigos RELAP4/MOD3 e RELAP4/MOD5 na simulacao da face de despressurizacao do acidente de perda de refrigerante primario na usina nuclear de Angra 1
Publishing Information
- Imprint Title
- Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 2
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 177-188.
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
- 20061087
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANGRA-1 REACTOR; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; R CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; PWR TYPE 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. 2.