To examine the applicability of Mini-CT (0.16T-CT) specimens to fracture toughness evaluation by Master Curve method, we conducted fracture toughness tests using specimens with different size and shapes such as pre-cracked Charpy-type, 0.4T-CT and 1T-CT in addition to 0.16T-CT specimens for commercially manufactured five kinds of SA533B Cl.1 steels with different ductile-to-brittle transition temperature. Reference temperature To determined by 0.16T-CT specimens were approximately equal to those of 1T-CT specimens for all materials. The Weibull slope of 0.16T-CT specimens was similar to those of other larger specimens. We also examined a loading rate effect on To of 0.16T-CT specimens within the quasi-static loading range prescribed by ASTM E1921. There was no loading rate effect peculiar to 0.16T-CT specimens, while the higher loading rate gave rise to slightly higher To.
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ASME 2013 Pressure Vessels and Piping Conference
July 14–18, 2013
Paris, France
Conference Sponsors:
- Pressure Vessels and Piping Division
- Nondestructive Evaluation Engineering Division
ISBN:
978-0-7918-5564-5
PROCEEDINGS PAPER
Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens
Tohru Tobita,
Tohru Tobita
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Yutaka Nishiyama,
Yutaka Nishiyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Takuyo Ohtsu,
Takuyo Ohtsu
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Makoto Udagawa,
Makoto Udagawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Jinya Katsuyama,
Jinya Katsuyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Kunio Onizawa
Kunio Onizawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Tohru Tobita
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Yutaka Nishiyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Takuyo Ohtsu
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Makoto Udagawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Jinya Katsuyama
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Kunio Onizawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
PVP2013-97897, V01BT01A043; 8 pages
Published Online:
January 17, 2014
Citation
Tobita, T, Nishiyama, Y, Ohtsu, T, Udagawa, M, Katsuyama, J, & Onizawa, K. "Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens." Proceedings of the ASME 2013 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Paris, France. July 14–18, 2013. V01BT01A043. ASME. https://doi.org/10.1115/PVP2013-97897
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