A probabilistic fracture mechanics (PFM) analysis method for pressure boundary components is useful to evaluate the structural integrity in a quantitative way. This is because the uncertainties related to influence parameters can be rationally incorporated in PFM analysis. From this viewpoint, the probabilistic approach evaluating through-wall cracking frequencies (TWCFs) of reactor pressure vessels (RPVs) has already been adopted as the regulation on fracture toughness requirements against PTS events in the U.S. As a study of applying PFM analysis to the integrity assessment of domestic RPVs, JAEA has been preparing input data and analysis models to calculate TWCFs using PFM analysis code PASCAL3. In this paper, activities have been introduced such as preparing input data and models for domestic RPVs, verification of PASCAL3, and formulating guideline on general procedures of PFM analysis for the purpose of utilizing PASCAL3. In addition, TWCFs for a model RPV evaluated by PASCAL3 are presented.
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ASME 2015 Pressure Vessels and Piping Conference
July 19–23, 2015
Boston, Massachusetts, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5693-2
PROCEEDINGS PAPER
Study on Application of PFM Analysis Method to Japanese Code for RPV Integrity Assessment Under PTS Events
Kazuya Osakabe,
Kazuya Osakabe
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
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Koichi Masaki,
Koichi Masaki
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
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Jinya Katsuyama,
Jinya Katsuyama
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
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Genshichiro Katsumata,
Genshichiro Katsumata
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
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Kunio Onizawa,
Kunio Onizawa
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
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Shinobu Yoshimura
Shinobu Yoshimura
The University of Tokyo, Tokyo, Japan
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Kazuya Osakabe
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
Koichi Masaki
Mizuho Information & Research Institute (MHIR), Tokyo, Japan
Jinya Katsuyama
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
Genshichiro Katsumata
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
Kunio Onizawa
Japan Atomic Energy Agency (JAEA), Tokai-mura, Ibaraki, Japan
Shinobu Yoshimura
The University of Tokyo, Tokyo, Japan
Paper No:
PVP2015-45497, V01BT01A055; 8 pages
Published Online:
November 19, 2015
Citation
Osakabe, K, Masaki, K, Katsuyama, J, Katsumata, G, Onizawa, K, & Yoshimura, S. "Study on Application of PFM Analysis Method to Japanese Code for RPV Integrity Assessment Under PTS Events." Proceedings of the ASME 2015 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Boston, Massachusetts, USA. July 19–23, 2015. V01BT01A055. ASME. https://doi.org/10.1115/PVP2015-45497
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