In recent years, cracks have been detected in piping systems of nuclear power plants. Many of them are multiple cracks in the same welded joints. Therefore, structural integrity evaluation and risk assessment considering multiple cracks and crack initiation in aged piping have become increasingly important. Probabilistic fracture mechanics (PFM) is a rational methodology in structural integrity evaluation and risk assessment of aged piping in nuclear power plants. Two PFM codes, PASCAL-SP and PRAISE-JNES, have been improved or developed in Japan for the structural integrity evaluation and risk assessment considering the age related degradation mechanisms of pipes. Although the purposes to develop these two codes are different, both have almost the same basic functions to obtain the failure probabilities of pipes. In this paper, a benchmark analysis was conducted considering multiple cracks and crack initiation, in order to confirm their reliability and applicability. Based on the numerical investigation in consideration of important influence factors such as crack number, crack location, crack distribution and crack detection probability of in-service inspection, it was concluded that the analysis results of these two codes are in good agreement.
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ASME 2014 Pressure Vessels and Piping Conference
July 20–24, 2014
Anaheim, California, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4598-1
PROCEEDINGS PAPER
Benchmark Analysis on Probabilistic Fracture Mechanics Analysis Codes Considering Multiple Cracks and Crack Initiation in Aged Piping of Nuclear Power Plants
Yinsheng Li,
Yinsheng Li
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Kazuya Osakabe,
Kazuya Osakabe
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
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Genshichiro Katsumata,
Genshichiro Katsumata
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Jinya Katsuyama,
Jinya Katsuyama
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Kunio Onizawa,
Kunio Onizawa
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
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Shinobu Yoshimura
Shinobu Yoshimura
The University of Tokyo, Tokyo, Japan
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Yinsheng Li
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Kazuya Osakabe
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
Genshichiro Katsumata
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Jinya Katsuyama
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Kunio Onizawa
Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki, Japan
Shinobu Yoshimura
The University of Tokyo, Tokyo, Japan
Paper No:
PVP2014-28513, V001T01A058; 8 pages
Published Online:
November 18, 2014
Citation
Li, Y, Osakabe, K, Katsumata, G, Katsuyama, J, Onizawa, K, & Yoshimura, S. "Benchmark Analysis on Probabilistic Fracture Mechanics Analysis Codes Considering Multiple Cracks and Crack Initiation in Aged Piping of Nuclear Power Plants." Proceedings of the ASME 2014 Pressure Vessels and Piping Conference. Volume 1: Codes and Standards. Anaheim, California, USA. July 20–24, 2014. V001T01A058. ASME. https://doi.org/10.1115/PVP2014-28513
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