Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation
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| Natura: | Artículo científico |
| Lingua: | en |
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Sociedade Brasileira de Proteção Radiológica - SBPR
2021
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| _version_ | 1876481740233506816 |
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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 |
| institution | Redalyc |
| 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 |