Published 1980 | Version v1
Book

Evaluation of structural welds with respect to reliability and inservice inspection

Creators

  • 1. Babcock - Brown Boveri Reaktor G.m.b.H., Mannheim (Germany, F.R.)

Description

The ongoing developments with respect to large forgings for nuclear pressure vessels and the present philosophy of inservice inspection in the Federal Republic of Germany (FRG) (inspection of weld regions only) seem to be oriented towards a monolithic pressure vessel requiring no inservice inspection. This raises questions as to the task of inservice inspection in the framework of the total reliability of a nuclear pressure vessel. The inherent 'weak spots' associated with welds of ferritic low alloyed steels are the microstructural features of stress relief cracks and regions of coarse grains. An analysis as to the effects of stress relief cracks and regions of coarse grains in the heat affected zones of welds on subcritical crack growth is performed. It is shown that these 'weak spots' cannot be considered a particular safety hazard to vessel integrity. Therefore welds per se should not constitute the criteria for the performance of inservice inspection. Rather, the inservice inspection programme should check the regions where manufacturing history, loading conditions, and materials degradation are expected to enhance subcritical crack growth. (author)

Additional details

Publishing Information

Publisher
Applied Science.
Imprint Place
London
ISBN
0-85334-872-3
Imprint Title
Trends in reactor pressure vessel and circuit development
Journal Page Range
p. 111-125.

Conference

Title
IAEA specialists meeting on trends in reactor pressure vessel and circuit development.
Dates
5 - 8 Mar 1979.
Place
Madrid, Spain.