Austenitic stainless steels in boiling water reactor (BWR) core structures can experience significant fracture toughness reductions at high fluence levels of neutron irradiation. To understand the fracture toughness reductions of irradiated austenitic stainless steels is very important for integrity estimation of core internals. Larger size specimen is needed to obtain the valid JIC of high fracture toughness material. However, it is generally difficult for irradiated material to prepare the enough big specimens for taking valid fracture toughness in ASTM E1820–06 since the material volume is restricted. Stretched zone which is generated between fatigue crack and dimple surface on the CT specimen fracture surface is said to have good linear relationship with JIC. New method for JIC estimation from small CT specimen using stretched zone width was investigated. Cold-worked SUS304 was used for investigation. 0.25–1.5TCT specimens with similar figure of standard dimensions and the CT specimens with different thickness from standard dimensions were prepared for JIC tests. The correlations of specimen width, thickness, critical stretched zone width, JQ and JIC were investigated. JQ obtained from J-R curve tended to decrease with specimen width in the case of similar figure. However, JQ tended to increase with thickness decrease in the case of CT specimen with different thickness from standard dimensions. On the other hand, critical stretched zone width showed the tendency to decrease with thickness decrease in the case of CT specimen with different thickness from standard dimensions. The equation for JIC estimation of invalid small CT specimens was designed by regression analysis using the above relationship. The prediction accuracy achieved within plus-minus 30%.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width
Tadahiko Torimaru,
Tadahiko Torimaru
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
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Masanari Sugiyama,
Masanari Sugiyama
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
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Hiroshi Sakamoto,
Hiroshi Sakamoto
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
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Shigeaki Tanaka,
Shigeaki Tanaka
Toshiba Corporation, Yokohama, Japan
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Tomomi Nakamura
Tomomi Nakamura
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Tadahiko Torimaru
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
Masanari Sugiyama
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
Hiroshi Sakamoto
Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki, Japan
Shigeaki Tanaka
Toshiba Corporation, Yokohama, Japan
Tomomi Nakamura
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Paper No:
ICONE17-75233, pp. 375-385; 11 pages
Published Online:
February 25, 2010
Citation
Torimaru, T, Sugiyama, M, Sakamoto, H, Tanaka, S, & Nakamura, T. "Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 375-385. ASME. https://doi.org/10.1115/ICONE17-75233
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