| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1570068 | Journal of Nuclear Materials | 2006 | 9 Pages |
Abstract
It is known that for Russian-type and Western water reactor pressure vessel steels there is a similar degradation in mechanical properties during equivalent neutron irradiation. Available surveillance results from WWER and PWR vessels are used in this article to compare irradiation damage evolution for the different reactor pressure vessel welds. The analysis is done through the semi-mechanistic model for radiation embrittlement developed by JRC-IE. Consistency analysis with BWR vessel materials and model alloys has also been performed within this study. Globally the two families of studied materials follow similar trends regarding the evolution of irradiation damage. Moreover in the high fluence range typical of operation of WWER the radiation stability of these vessels is greater than the foreseen one for PWR.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
L. Debarberis, B. Acosta, A. Zeman, F. Sevini, A. Ballesteros, A. Kryukov, F. Gillemot, M. Brumovsky,