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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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| Formato: | Artigo |
| Idioma: | Inglês |
| Publicado em: |
Hindawi Limited
2014-01-01
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| Colecção: | Science and Technology of Nuclear Installations |
| Acesso em linha: | http://dx.doi.org/10.1155/2014/150985 |
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