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 irradation.
Available surveillance results from WWER and PWER 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.
DEBARBERIS Luigi;
ACOSTA IBORRA Beatriz;
SEVINI Filippo;
ZEMAN Andrej;
BALLESTEROS A.;
KRYUKOV A.;
GILLEMOT F.;
BRUMOVSKY M.;
2006-04-04
ELSEVIER SCIENCE BV
JRC30648
https://publications.jrc.ec.europa.eu/repository/handle/JRC30648,
| Name | Country | City | Type |
|---|
This document is only visible at the Commission level.
You are not authorized to publish or distribute it outside the European Commission.
This is a public document. You can share this publication.
Datasets
| ID | Title | Public URL |
|---|
Dataset collections
| ID | Acronym | Title | Public URL |
|---|
Scripts / source codes
| Description | Public URL |
|---|
Additional supporting files
| File name | Description | File type |
|---|