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Autor principal: Eduardo Madeira Borges
Formato: Artículo científico
Lenguaje:en
Publicado: Sociedade Brasileira de Proteção Radiológica - SBPR 2021
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Acceso en línea:https://www.redalyc.org/articulo.oa?id=722280949005
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author Eduardo Madeira Borges
author_facet Eduardo Madeira Borges
contents Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation Eduardo Madeira Borges Gaianê Sabundjian Biología ANGRA 2 RELAP5 code Safety analysis Nuclear reactor The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core. 2021 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280949005 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.2B Vol.9
format Artículo científico
id redalyc_722280949005
language en
publishDate 2021
publisher Sociedade Brasileira de Proteção Radiológica - SBPR
spellingShingle Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation
Eduardo Madeira Borges
Biología
ANGRA 2
RELAP5 code
Safety analysis
Nuclear reactor
Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation Eduardo Madeira Borges Gaianê Sabundjian Biología ANGRA 2 RELAP5 code Safety analysis Nuclear reactor The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core. 2021 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280949005 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.2B Vol.9
title Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation
topic Biología
ANGRA 2
RELAP5 code
Safety analysis
Nuclear reactor
url https://www.redalyc.org/articulo.oa?id=722280949005