Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors
The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 pla...
Gorde:
| Egile Nagusiak: | , |
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| Formatua: | Artigo |
| Hizkuntza: | Inglês |
| Argitaratua: |
Elsevier
2017-08-01
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| Saila: | Nuclear Engineering and Technology |
| Gaiak: | |
| Sarrera elektronikoa: | http://www.sciencedirect.com/science/article/pii/S1738573316303503 |
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