Irradiation embrittlement and mitigation. V. 1. Working material. Proceedings of a specialists meeting held in Espoo, Finland 23-26 October 1995

The purpose of the meeting was to provide an international forum for discussion on recent results in research and utility experience on radiation damage and its surveillance, annealing and re-embrittlement of PWR, WWER and BWR reactor pressure vessel materials. The scope included: mechanism of radiation damage; effects of operating parameters (flux, temperature, time, etc.); results from surveillance programmes and their analysis; fracture mechanics testing and evaluation; annealing and optimization of the process; re-embrittlement after annealing; Presentations were aimed at better understanding of radiation damage, annealing and re-irradiation behaviour of reactor pressure vessels materials, at providing guidance and recommendations for optimization of annealing and surveillance programmes and directions for further investigations. Refs, figs and tabs