Published September 1980 | Version v1
Journal article

Applications of probabilistic fracture mechanics to light water reactor pressure vessels and piping

Creators

  • 1. UKAEA Atomic Energy Research Establishment, Harwell. Theoretical Physics Div.

Description

This paper reviews recent calculations of the statistical reliability of LWR reactor vessels and piping. The broad theoretical principles of these calculations are well established and it is therefore possible to compare the physical assumptions made in different calculations. Such a comparison shows that certain functions are not known at all well; for example, (i) the frequency of occurrence of cracks in weld-regions, (ii) the size distribution of cracks, (iii) the efficiency of methods of non-destructive examination and (iv) the transient loadings that the system experiences in service. On the other hand, relevant materials properties (toughness, crack growth characteristics) appear to be known adequately if not completely. Despite these quantitative uncertainties in the input, it seems possible to draw several broad conclusions from the results of these calculations. These concern (i) the low absolute rates of failures, (ii) the way these depend upon time in service, (iii) the effect upon them of in-service inspection and (iv) their sensitivity or otherwise to the physical assumptions which are made. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
60
Journal Issue
1
Series
Nucl. Eng. Des.
Journal Page Range
49-56
ISSN
0029-5493

Conference

Title
2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants.
Dates
20 - 21 Aug 1979.
Place
Berlin, Germany, F.R.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
12582220
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; FRACTURE MECHANICS; PIPES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; STEAM LINES
Descriptors DEC
CONTAINERS; MECHANICS; PIPELINES; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS