The integrity of the pressure vessel is vital to the safe operation of a nuclear reactor. It is therefore necessary to monitor or predict the changes in the pressure vessel material during operation. Exposure to irradiation (or elevated temperatures) causes the segregation of phosphorus to internal grain boundaries in RPV steels. This, in turn, encourages brittle intergranular failure of the material. The objectives of PISA are to improve predictability of a failure mechanism that can affect all types of reactor plant operating in Europe, and in particular to improve the predictability of mechanical property changes in long- service steels for plant applications.
Funding SchemeCSC - Cost-sharing contracts
1755 ZG Petten
77818 Moret Sur Loing
GL13 9PB Berkeley
250 68 Rez - Praha
28709 San Sebastian De Los Reyes - Madrid
L69 3GH Liverpool