Community Research and Development Information Service - CORDIS

Abstract

This paper reviews the major developments and trends in the technical areas covered by Division G of SMIRT since 1971. Initially its work was devoted to steel reactor pressure vessels for light water reactors (LWRs). Emphasis has moved from stress analysis of particular regions of pressure vessel components to fracture mechanics and failure assessment. More recently the terms of reference have been redefined to concentrate on failure assessment aspects of all non-fuel steel reactor components. The reviews cover work on the topics of structural integrity of pressure components, materials aspects, fracture mechanics and non-destructive examination, and also discuss further developments.

Additional information

Authors: CRUTZEN S, JRC Ispra (IT);NICHOLS R, Nichols Consultancies, Warrington (GB);KUSSMAUL K, MPA, Universität Stuttgart (DE);YAGAWA G, University of Tokyo (JP)
Bibliographic Reference: Article: Nuclear Engineering and Design (1991) pp. 219-259
Record Number: 199111589 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en