Flaw assessment procedure for high temperature reactor components
Creators
- 1. Nuclear Electric PLC, Berkeley (UK). Berkeley Nuclear Labs.
- 2. Oak Ridge National Lab., TN (USA)
- 3. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
Description
An interim high-temperature flaw assessment procedure is described. This is a result of a collaborative effort between Electric Power Research Institute in the USA, Central Research Institute of Electric Power Industry in Japan, and Nuclear Electric plc in the UK. The procedure addresses preexisting defects subject to creep-fatigue loading conditions. Laws employed to calculate the crack growth per cycle are defined in terms of fracture mechanics parameters and constants related to the component material. The crack growth laws may be integrated to calculate the remaining life of a component or to predict the amount of crack extension in a given period. Fatigue and creep crack growth per cycle are calculated separately, and the total crack extension is taken as the simple sum of the two contributions. An interaction between the two propagation modes is accounted for in the material properties in the separate calculations. In producing the procedure, limitations of the approach have been identified. Some of these limitations are to be addressed in an extension of the current collaborative program. 20 refs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90015543; OSTI; INIS; US Govt. Printing Office Dep.Files
22004588.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- CONF-901109--12
Conference
- Title
- International symposium on gas-liquid two-phase flows in conjunction with the winter annual meeting of the American Society of Mechanical Engineers.
- Dates
- 25-30 Nov 1990.
- Place
- Dallas, TX (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22004588
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COORDINATED RESEARCH PROGRAMS; CRACK PROPAGATION; CRACKS; CREEP; DEFORMATION; ELASTICITY; EPRI; FATIGUE; FRACTURE MECHANICS; JAPAN; LMFBR TYPE REACTORS; MATERIALS TESTING; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTOR MATERIALS; SENSITIVITY ANALYSIS; SPECIFICATIONS; STRESS ANALYSIS; UNITED KINGDOM
- Descriptors DEC
- ASIA; BREEDER REACTORS; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; REACTORS; RESEARCH PROGRAMS; TESTING
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400