Published 1990 | Version v1
Report Open

Flaw assessment procedure for high temperature reactor components

  • 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.

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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).

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400