The Master Curve method has been proposed and recognized worldwide as an alternative approach to evaluate fracture toughness of reactor pressure vessel (RPV) steels in brittle-to-ductile transition temperature range. This method theoretically provides the confidence levels of fracture toughness in consideration of the statistical distribution, which is an inherent property of fracture toughness. In this study, a series of fracture toughness tests was conducted for typical Japanese RPV steels, SFVQ1A and SQV2A, to identify the effects of test temperature, specimen size, and loading rate, and the applicability of the Master Curve method was experimentally validated. The differences in test temperature and specimen size did not affect master curves. In contrast, increasing loading rate significantly shifted master curves to higher temperatures. The lower bound curve based on the master curve could conservatively envelop all of the experimental fracture toughness data. The present rule, in which the lower limit of fracture toughness is indirectly determined by Charpy impact test results, can be too conservative, while the application of the Master Curve method may significantly reduce the conservativity of the allowable level of fracture toughness.
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ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
July 23–27, 2006
Vancouver, BC, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4758-6
PROCEEDINGS PAPER
Applicability of Master Curve Method to Japanese Reactor Pressure Vessel Steels
Naoki Miura,
Naoki Miura
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
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Naoki Soneda,
Naoki Soneda
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
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Taku Arai,
Taku Arai
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
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Kenji Dohi
Kenji Dohi
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
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Naoki Miura
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
Naoki Soneda
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
Taku Arai
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
Kenji Dohi
Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
Paper No:
PVP2006-ICPVT-11-93792, pp. 371-378; 8 pages
Published Online:
July 23, 2008
Citation
Miura, N, Soneda, N, Arai, T, & Dohi, K. "Applicability of Master Curve Method to Japanese Reactor Pressure Vessel Steels." Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference. Volume 7: Operations, Applications, and Components. Vancouver, BC, Canada. July 23–27, 2006. pp. 371-378. ASME. https://doi.org/10.1115/PVP2006-ICPVT-11-93792
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