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Wilkowski, G.; Schmidt, R.; Scott, P.
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Battelle, Columbus, OH (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1997
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Battelle, Columbus, OH (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1997
AbstractAbstract
[en] This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program
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Jun 1997; 332 p; Also available from OSTI as TI97006968; NTIS; GPO
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Report
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