Published 1987
| Version v1
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Utilization of Relap 5 computer code for analyzing thermohydraulic projects
- 1. Pernambuco Univ., Recife (Brazil). Dept. de Energia Nuclear
Description
This work deals with the design of a scaled test facility of a typical pressurized water reactor plant of the 1300 MW (electric) class. A station blackout has been choosen to investigate the thermohydraulic behaviour of the the test facility in comparison to the reactor plant. The computer code RELAPS/MOD1 has been utilized to simulate the blackout and to compare the test facility behaviour with the reactor plant one. The results demonstrate similar thermohydraulic behaviours of the two systems. (author)
Abstract (Portuguese)
Este trabalho trata do dimensionamento de uma instalacao experimental escalada com referencia a uma central nuclear com reator a agua leve pressurizada da classe 1300 MW (eletricos). Um ''blackout'' da usina foi escolhido para investigar o comportamento termohidraulico da instalacao experimental comparado ao da central nuclear. O codigo computacional RELAPS/MOD1 foi utilizado para simular o blackout e comparar o comportamento da instalacao experimental frente ao comportamento da central nuclear. Os resultados demonstram comportamentos termohidraulicos similares dos dois sistemas. (autor)Files
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Additional details
Additional titles
- Original title (Portuguese)
- Utilizacao do codigo computacional Relap 5 em projetos termo-hidraulicos
Publishing Information
- Imprint Pagination
- 3 p.
- Report number
- INIS-BR--1168
Conference
- Title
- 9. Brazilian Congress of Mechanical Engineering.
- Dates
- 7-11 Dec 1987.
- Place
- Florianopolis, SC (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 19073149
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; FLUID FLOW; HEAT TRANSFER; PWR TYPE REACTORS; R CODES; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS