The hardening and embrittlement of Reactor Pressure Vessel (RPV)-steels is of great concern in the actual nuclear power plant life assessment. This embrittlement is caused by irradiation-induced damage, like vacancies, interstitials, solutes and their clusters. An established and accepted understanding of the mechanisms responsible for this phenomenon is required. The aim of this project is to develop predictive tools, by combination of advanced experimental techniques and computer simulations.
|Title of host publication||Proceedings of the 7th FirW PhD Symposium - http://symposium.elis.ugent.be/index.php?section=prgposters〈=nl|
|Place of Publication||Ghent, Belgium|
|State||Published - Dec 2006|
|Event||7th FirW PhD Symposium. - FirW UGent, Ghent|
Duration: 29 Nov 2006 → 29 Nov 2006
|Conference||7th FirW PhD Symposium.|
|Period||2006-11-29 → 2006-11-29|