PROBABILITY OF THE RUPTURING OF REACTOR VESSELS DUE TO WATER UNDER PRESSURE
In 1976 the French Commissariat a l'Energie Atomique (DSN), the Commission of the European Communities (Ispra J.R.C.) and Framatome set up a joint committee to direct a research program with the task of developing a method of assessing pressure vessel fast fracture probability and implementing the required computer codes. The method used is based on the application of probabilistic fracture mechanics on statistical distributions of data concerning flaws, material properties and loading conditions of reactor P.V.. It estimates the evolution of an initial population of defects during reactor life due to fatigue propagation (for conditions of repeated loadings) and the probability of their unstable propagation, at any time in reactor life, due to emergency and faulty conditions. Parameters such as, environmental conditions, neutron embrittlement, position of the cracks, etc. are taken into account. All input data are introduced in the COVASTOL as histograms, built up on the basis of experimental data.
Bibliographic Reference: EUR 8682 EN-FR (1983) MF, 352 P., BFR 480, BLOW-UP COPY BFR 1760, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989122063700 / Last updated on: 1987-01-01
Available languages: en,fr