MODELING LOFW IN A PWR USING MELCOR
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| Format: | Artículo científico |
| Language: | en |
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Sociedade Brasileira de Proteção Radiológica - SBPR
2020
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| _version_ | 1876454492792160256 |
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| author | Maritza Rodríguez Gual |
| author_facet | Maritza Rodríguez Gual |
| contents | MODELING LOFW IN A PWR USING MELCOR Maritza Rodríguez Gual Marcos C. Maturana Nathália N. Araújo Marcelo R. Martins Biología PSA MELCOR Severe accident The Probabilistic Safety Assessment (PSA) is part of a Nuclear Power Plant (NPP) licensing process. It considers the elaboration and updating of probabilistic models that estimate the risk associated with the operation, allowing the risk monitoring from the design to the plant decommissioning, for both operational as regulatory activities. The PSA identifies those components or plant systems whose unavailability contributes significantly to the Core Damage Frequency (CDF) and to the Large Early Release Frequency (LERF) of radioactive material. Based on the PSA Level 1 results for a reference plant under design, the Analysis, Evaluating and Risk Management Laboratory (LabRisco), located in the University of São Paulo (USP), Brazil, started the analytical investigation of severe accident phenomena using the US Nuclear Regulatory Commission (NRC) MELCOR2.2 code – focusing on the qualification of a group of specialists who will subsidize a PSA Level 2 for the same plant. This PSA Level 1 shows that the accident with large CDF contribution is the Loss of Feed Water Accident (LOFW). Therefore, the initial objective of the investigation was to model the progression of severe accidents during a LOFW for the reference Pressurized Water Reactor (PWR) and to analyze the response of the plant under these accident scenarios. During the course of the hypothetical LOFW in the reference plant, hydrogen was generated – by a reaction between the water and the fuel-clad metal inside the reactor pressure vessel (RPV) but not representing a serious threat to the RPV integrity. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280924013 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.3A Vol.8 |
| format | Artículo científico |
| id | redalyc_722280924013 |
| institution | Redalyc |
| language | en |
| publishDate | 2020 |
| publisher | Sociedade Brasileira de Proteção Radiológica - SBPR |
| spellingShingle | MODELING LOFW IN A PWR USING MELCOR Maritza Rodríguez Gual Biología PSA MELCOR Severe accident MODELING LOFW IN A PWR USING MELCOR Maritza Rodríguez Gual Marcos C. Maturana Nathália N. Araújo Marcelo R. Martins Biología PSA MELCOR Severe accident The Probabilistic Safety Assessment (PSA) is part of a Nuclear Power Plant (NPP) licensing process. It considers the elaboration and updating of probabilistic models that estimate the risk associated with the operation, allowing the risk monitoring from the design to the plant decommissioning, for both operational as regulatory activities. The PSA identifies those components or plant systems whose unavailability contributes significantly to the Core Damage Frequency (CDF) and to the Large Early Release Frequency (LERF) of radioactive material. Based on the PSA Level 1 results for a reference plant under design, the Analysis, Evaluating and Risk Management Laboratory (LabRisco), located in the University of São Paulo (USP), Brazil, started the analytical investigation of severe accident phenomena using the US Nuclear Regulatory Commission (NRC) MELCOR2.2 code – focusing on the qualification of a group of specialists who will subsidize a PSA Level 2 for the same plant. This PSA Level 1 shows that the accident with large CDF contribution is the Loss of Feed Water Accident (LOFW). Therefore, the initial objective of the investigation was to model the progression of severe accidents during a LOFW for the reference Pressurized Water Reactor (PWR) and to analyze the response of the plant under these accident scenarios. During the course of the hypothetical LOFW in the reference plant, hydrogen was generated – by a reaction between the water and the fuel-clad metal inside the reactor pressure vessel (RPV) but not representing a serious threat to the RPV integrity. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280924013 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.3A Vol.8 |
| title | MODELING LOFW IN A PWR USING MELCOR |
| topic | Biología PSA MELCOR Severe accident |
| url | https://www.redalyc.org/articulo.oa?id=722280924013 |