Published 1987
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Utilization of a statistical procedure for DNBR calculation and in the survey of reactor protection limits
Description
A new procedure is applied to Angra 1 NPP, which is related to DNBR calculations, considering the design parameters statistically: Improved Thermal Design Procedure (ITDP). The ITDP application leads to the determination of uncertainties in the input parameters, the sensitivity factors on DNBR. The DNBR limit and new reactor protection limits. This was done to Angra 1 with the subchannel code COBRA-IIIP. The analysis of limiting accident in terms of DNB confirmed a gain in DNBR margin, and greater operation flexibility of the plant, decreasing unnecessary trips of the reactor. (author)
Abstract (Portuguese)
Foi aplicado para Angra 1 um novo procedimento de calculo de DNBR proposto pela Westinghouse, ''Improved Thermal Design Procedure'' ITDP, que trata os parametros de projeto estatisticamente. A aplicacao do ITDP implica na determinacao das incertezas nos parametros de projeto, de fatores de sensibilidade do DNBR a estes parametros, no estabelecimento de um novo DNBR limite e de novas curvas limites para o sistema de protecao do reator. Isto foi feito para Angra 1 atraves de simulacoes do nucleo com o codigo com o codigo de subcanais COBRA-IIIP. A analise do acidente limitante de projeto para DNB confirmou um ganho de margem em DNBR, garantindo tambem uma maior flexibilidade operacional, reduzindo desligamentos desnecessarios do reator. (autor)Files
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Additional details
Additional titles
- Original title (Portuguese)
- Aplicacao do tratamento estatistico no calculo do DNBR e no levantamento de curvas limites de protecao do reator de Angra 1
Publishing Information
- Imprint Pagination
- 139 p.
- Report number
- CNEN-DR-GTT--04/87
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 19073128
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANGRA-1 REACTOR; C CODES; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DEPARTURE NUCLEATE BOILING; MATHEMATICAL MODELS; REACTOR PROTECTION SYSTEMS; SENSITIVITY ANALYSIS
- Descriptors DEC
- BOILING; COMPUTER CODES; ENRICHED URANIUM REACTORS; EVALUATION; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS