A Critical Heat Generation for Safe Nuclear Fuels after a LOCA
This study applies a thermo-elasto-plastic-creep finite element procedure to the analysis of an accidental behavior of nuclear fuel as well as normal behavior. The result will be used as basic data for the robust design of nuclear power plant and fuels. We extended the range of mechanical strain fro...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2014-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2014/150985 |
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| author | Jae-Yong Kim Dong-Bock Kim Hee-Jeong Cho Soon-Bum Kwon Young-Doo Kwon |
| author_facet | Jae-Yong Kim Dong-Bock Kim Hee-Jeong Cho Soon-Bum Kwon Young-Doo Kwon |
| author_sort | Jae-Yong Kim |
| collection | DOAJ |
| description | This study applies a thermo-elasto-plastic-creep finite element procedure to the analysis of an accidental behavior of nuclear fuel as well as normal behavior. The result will be used as basic data for the robust design of nuclear power plant and fuels. We extended the range of mechanical strain from small or medium to large adopting the Hencky logarithmic strain measure in addition to the Green-Lagrange strain and Almansi strain measures, for the possible large strain situation in accidental environments. We found that there is a critical heat generation after LOCA without ECCS (event category 5), under which the cladding of fuel sustains the internal pressure and temperature for the time being for the rescue of the power plant. With the heat generation above the critical value caused by malfunctioning of the control rods, the stiffness of cladding becomes zero due to the softening by high temperature. The weak position of cladding along the length continuously bulges radially to burst and to discharge radioactive substances. This kind of cases should be avoid by any means. |
| format | Article |
| id | doaj-art-fb02c2ed2a874810b104f2ee93593629 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2014-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-fb02c2ed2a874810b104f2ee935936292025-08-20T03:25:56ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832014-01-01201410.1155/2014/150985150985A Critical Heat Generation for Safe Nuclear Fuels after a LOCAJae-Yong Kim0Dong-Bock Kim1Hee-Jeong Cho2Soon-Bum Kwon3Young-Doo Kwon4Korea Atomic Energy Research Institute, No. 111 Daedeokdaero 989 Road, Daejeon 305-353, Republic of KoreaDepartment of Global Marketing, Modeun Elevator Co., Ltd., No. 241 Ilbansaneop-gil Geochang-gun, Kyungsangnam-do, Namsang-myeon 670-881, Republic of KoreaGraduate School of Mechanical Engineering, Kyungpook National University, No. 80 Daehakro, Daegu 702-701, Republic of KoreaSchool of Mechanical Engineering & IEDT, Kyungpook National University, No. 80 Daehakro, Daegu 702-701, Republic of KoreaSchool of Mechanical Engineering & IEDT, Kyungpook National University, No. 80 Daehakro, Daegu 702-701, Republic of KoreaThis study applies a thermo-elasto-plastic-creep finite element procedure to the analysis of an accidental behavior of nuclear fuel as well as normal behavior. The result will be used as basic data for the robust design of nuclear power plant and fuels. We extended the range of mechanical strain from small or medium to large adopting the Hencky logarithmic strain measure in addition to the Green-Lagrange strain and Almansi strain measures, for the possible large strain situation in accidental environments. We found that there is a critical heat generation after LOCA without ECCS (event category 5), under which the cladding of fuel sustains the internal pressure and temperature for the time being for the rescue of the power plant. With the heat generation above the critical value caused by malfunctioning of the control rods, the stiffness of cladding becomes zero due to the softening by high temperature. The weak position of cladding along the length continuously bulges radially to burst and to discharge radioactive substances. This kind of cases should be avoid by any means.http://dx.doi.org/10.1155/2014/150985 |
| spellingShingle | Jae-Yong Kim Dong-Bock Kim Hee-Jeong Cho Soon-Bum Kwon Young-Doo Kwon A Critical Heat Generation for Safe Nuclear Fuels after a LOCA Science and Technology of Nuclear Installations |
| title | A Critical Heat Generation for Safe Nuclear Fuels after a LOCA |
| title_full | A Critical Heat Generation for Safe Nuclear Fuels after a LOCA |
| title_fullStr | A Critical Heat Generation for Safe Nuclear Fuels after a LOCA |
| title_full_unstemmed | A Critical Heat Generation for Safe Nuclear Fuels after a LOCA |
| title_short | A Critical Heat Generation for Safe Nuclear Fuels after a LOCA |
| title_sort | critical heat generation for safe nuclear fuels after a loca |
| url | http://dx.doi.org/10.1155/2014/150985 |
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