Published 2000
| Version v1
Computer medium
Analysis of the containment of a compact reactor PWR submitted to loss of coolant accident
- 1. Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)
Description
In the present paper analyses were done with the computer code RELAP5/MOD2 for rising the process conditions of the containment of a compact reactor PWR of low potency, submitted to Loss of Coolant Accidents (LOCA). The main results obtained were the behavior of maximum conditions of pressure as a function of the available containment free volume. It was also studied the problem of containment sub-compartmentation, that is to say, the possibility of the rupture to happen in restricted spaces generating high sub-compartment peak pressure and, consequently, high strains on the internal structures. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Analise da contencao de um reator PWR compacto submetido a acidente de perda de refrigerante
Publishing Information
- Imprint Title
- Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [800 p.]
- Journal Page Range
- p. 734-737
Conference
- Title
- 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications
- Original Conference Title
- 12. Encontro nacional de fisica de reatores e termo-hidraulica
- Dates
- 5-20 Oct 2000
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 32022835
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT; EXPERIMENTAL DATA; LOSS OF COOLANT; PRESSURE DEPENDENCE; PWR TYPE REACTORS; R CODES; TEMPERATURE DEPENDENCE; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs., 1 fig., 6 graphs Imprint:Published only in CD-Rom. Available from the Library of the Brazilian Nuclear Energy Commission, Rio de Janeiro;Futuro nuclear: refletindo para construir. Anais do 12. Encontro nacional de fisica de reatores e termo-hidraulica; 8. Congresso geral de energia nuclear; 5. Encontro nacional de aplicacoes nucleares