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1
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33745191290
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Stress corrosion damage estimation of the core shroud based on JSME NA1-2002 standard
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in Japanese
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S. Suzuki, K. Kumagai, Y. Okamura, T. Fukuda, Y. Yamashita and N. Yamashita, "Stress Corrosion Damage Estimation of the core shroud based on JSME NA1-2002 standard, Maintenology Vol.3 No.2, 2004 (in Japanese)
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(2004)
Maintenology
, vol.3
, Issue.2
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Suzuki, S.1
Kumagai, K.2
Okamura, Y.3
Fukuda, T.4
Yamashita, Y.5
Yamashita, N.6
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2
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33747621727
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Evaluation of SCC morphology on L-grade stainless steel in BWRs
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in Japanese
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S. Suzuki, K. Takamori, K. Kumagai, S. Ooki, T. Fukuda, Y. Yamashita and T. Futami, "Evaluation of SCC Morphology on L-grade Stainless Steel in BWRs", Journal of High Pressure Institute of Japan Vol.42 No.4 p197 2004 (in Japanese)
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(2004)
Journal of High Pressure Institute of Japan
, vol.42
, Issue.4
, pp. 197
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-
Suzuki, S.1
Takamori, K.2
Kumagai, K.3
Ooki, S.4
Fukuda, T.5
Yamashita, Y.6
Futami, T.7
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3
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7744228580
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Evaluation of IGSCC growth behaveior of 316NG PLR piping in BWR
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Kumagai, K., Suzuki, S., Mizutani, J., Shitara, C., Yonekura, K., Mastuda, M. and Futami, T. ; "Evaluation of IGSCC growth behaveior of 316NG PLR piping in BWR", Proc. Of 2004 ASME / JSME Pressure Vessel and Piping Conference.
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Proc. of 2004 ASME / JSME Pressure Vessel and Piping Conference
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Kumagai, K.1
Suzuki, S.2
Mizutani, J.3
Shitara, C.4
Yonekura, K.5
Mastuda, M.6
Futami, T.7
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5
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33745228205
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Crack growth behavior of irradiated type 304L stainless steel in simulated BWR environment
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Stevenson, Washington
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Anders Jenssen, Pal Efsing, Karen Gott and Per-Olof Andersson, "Crack Growth Behavior of Irradiated Type 304L Stainless Steel in Simulated BWR Environment", Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, Stevenson, Washington, 2003.
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(2003)
Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -water Reactors
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Jenssen, A.1
Efsing, P.2
Gott, K.3
Andersson, P.-O.4
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7
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0002471464
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Mechanical properties of various kind of irradiated austenitic stainless steel
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American Nuclear Society, La Grange Park, IL
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M. Kodama, S. Suzuki, K. Nakata, S. Nishimura, K. Fukuya, T. Kato, Y. Tanaka, and S.Shima., "Mechanical Properties of Various Kind of Irradiated Austenitic Stainless Steel", Proc. Eighth International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, American Nuclear Society, La Grange Park, IL, 1997.
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(1997)
Proc. Eighth International Conference on Environmental Degradation of Materials in Nuclear Power Systems -water Reactors
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Kodama, M.1
Suzuki, S.2
Nakata, K.3
Nishimura, S.4
Fukuya, K.5
Kato, T.6
Tanaka, Y.7
Shima, S.8
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8
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28844500475
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Crack growth rate of hardened austenitic stainless steels in BWR and PWR environments
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Stevenson, Washington
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M. L. Castano Martin, M. S. Garcia Redondo, G. de Diego Velasco and D. Gomez Briceno, "Crack Growth Rate of Hardened Austenitic Stainless Steels in BWR and PWR Environments", Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, Stevenson, Washington, 2003.
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(2003)
Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -water Reactors
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-
Castano Martin, M.L.1
Garcia Redondo, M.S.2
De Diego Velasco, G.3
Gomez Briceno, D.4
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9
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7644243768
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Quantification of yield strength effects on IGSCC of austenitic stainless steel in high temperature water
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Stevenson, Washington
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Tetsuo Shoji, Guangfu Li, Junhyun Kwon, Shinobu Matsushima and Zhanpeng Lu, "Quantification of Yield Strength Effects on IGSCC of Austenitic Stainless Steel in High Temperature Water", Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, Stevenson, Washington, 2003.
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(2003)
Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -water Reactors
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Shoji, T.1
Li, G.2
Kwon, J.3
Matsushima, S.4
Lu, Z.5
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10
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33745191956
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Neutron flux effects on the irradiation hardening of type 304 stainless steel
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Boston, 8-10 June, to be published
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T.Torimaru, M.Kodama, S.Tanaka, T.Nakamura, K.Asano, and K.Kumagai, "Neutron Flux Effects on the Irradiation Hardening of Type 304 Stainless Steel," Proceedings at the 22nd Symposium on Effects of Radiation on Materials, Boston, 8-10 June 2004, to be published.
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(2004)
Proceedings at the 22nd Symposium on Effects of Radiation on Materials
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Torimaru, T.1
Kodama, M.2
Tanaka, S.3
Nakamura, T.4
Asano, K.5
Kumagai, K.6
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11
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84867625116
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Crack growth behavior or irradiated austenitic stainless steels in high-purity water at 289C
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Stevenson, Washington
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O.K.Chopra, E.E.Gruber, and W.J.Shack, "Crack Growth Behavior or Irradiated Austenitic Stainless Steels in High-Purity Water at 289C", Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, Stevenson, Washington, 2003.
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(2003)
Proc. Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -water Reactors
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Chopra, O.K.1
Gruber, E.E.2
Shack, W.J.3
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12
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33745193577
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Documents presented at the Structural Integrity Evaluation Committee, NISA
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Documents presented at the Structural Integrity Evaluation Committee, NISA.
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