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