Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress
Uncertainty of a severe accident code output needs to be handled reliably considering its use in safety regulation of nuclear industry. In particular, severe accident codes are utilized for probabilistic safety assessment (PSA), where the uncertainty of severe accident progress should be considered...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2018-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2018/5706409 |
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| _version_ | 1832562973709697024 |
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| author | Wonjun Choi Taeseok Kim Joongoo Jeon Nam Kyung Kim Sung Joong Kim |
| author_facet | Wonjun Choi Taeseok Kim Joongoo Jeon Nam Kyung Kim Sung Joong Kim |
| author_sort | Wonjun Choi |
| collection | DOAJ |
| description | Uncertainty of a severe accident code output needs to be handled reliably considering its use in safety regulation of nuclear industry. In particular, severe accident codes are utilized for probabilistic safety assessment (PSA), where the uncertainty of severe accident progress should be considered carefully due to its influence on human reliability analysis. Therefore, in this study, the uncertainty analysis of severe accident progress was performed using MELCOR code, and a total of 200 data sets of in-vessel uncertainty parameters were generated by Latin hypercube sampling method. The rank regression analysis was also performed to investigate the effect of uncertainty parameters on the severe accident progress. Sensitivity coefficients (SCs) in MELCOR such as molten clad drainage rate and zircaloy melt breakout temperature showed significant influence on relocation time and dryout time of lower plenum. However, the influence of uncertainty parameter diminished as the accident progressed. |
| format | Article |
| id | doaj-art-bf1eef555667467b9d3af099eb048a28 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2018-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-bf1eef555667467b9d3af099eb048a282025-02-03T01:21:18ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/57064095706409Effect of Molten Corium Behavior Uncertainty on the Severe Accident ProgressWonjun Choi0Taeseok Kim1Joongoo Jeon2Nam Kyung Kim3Sung Joong Kim4Department of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaDepartment of Nuclear Engineering, Hanyang University, Seoul 04763, Republic of KoreaUncertainty of a severe accident code output needs to be handled reliably considering its use in safety regulation of nuclear industry. In particular, severe accident codes are utilized for probabilistic safety assessment (PSA), where the uncertainty of severe accident progress should be considered carefully due to its influence on human reliability analysis. Therefore, in this study, the uncertainty analysis of severe accident progress was performed using MELCOR code, and a total of 200 data sets of in-vessel uncertainty parameters were generated by Latin hypercube sampling method. The rank regression analysis was also performed to investigate the effect of uncertainty parameters on the severe accident progress. Sensitivity coefficients (SCs) in MELCOR such as molten clad drainage rate and zircaloy melt breakout temperature showed significant influence on relocation time and dryout time of lower plenum. However, the influence of uncertainty parameter diminished as the accident progressed.http://dx.doi.org/10.1155/2018/5706409 |
| spellingShingle | Wonjun Choi Taeseok Kim Joongoo Jeon Nam Kyung Kim Sung Joong Kim Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress Science and Technology of Nuclear Installations |
| title | Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
| title_full | Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
| title_fullStr | Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
| title_full_unstemmed | Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
| title_short | Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress |
| title_sort | effect of molten corium behavior uncertainty on the severe accident progress |
| url | http://dx.doi.org/10.1155/2018/5706409 |
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