Abstract
A model based on key embrittlement mechanisms is proposed for the
analysis. The advantages of such semi-mechanistic model, when compared
to non-mechanistic models, is that it allows improved fitting of data
and permits the visualization of the relative contribution to
embrittlement of the various damage components. Data from a set of model
alloys with parametric variation of the Cu, P and Ni contents,
irradiated in the High Flux Reactor Petten (The Netherlands) and Kola
Nuclear Power Plant (Russia), have been thoroughly analysed. The low Ni
model alloys results are studied in detail showing the semi-mechanistic
model capabilities and their potential for application to commercial
steels and welds; in particular for those used in Russian pressure water
reactor (VVER). The additional effect of Ni and its influence in the
model are also presented in this article.
| Original language | English |
|---|---|
| Pages (from-to) | 210-216 |
| Journal | Journal of Nuclear Materials |
| Volume | 336 |
| Issue number | 2-3 |
| DOIs | |
| Publication status | Published - 2005 |
| MoE publication type | A1 Journal article-refereed |
Keywords
- radiation
- embrittlement
- irradiation embrittlement
- pressure vessels
- reactor pressure vessel embrittlement
- reactor pressure vessel steel
- alloys