General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor

Shigeki Kasahara; Junya Kaneda; Yumiko Tsuchiya; Satoshi Mimura; Minoru Narui; Masanori Yamazaki; Tatsuo T. Shikama; Hideki Matsui

General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor

Shigeki Kasahara, Junya Kaneda, Yumiko Tsuchiya, Satoshi Mimura, Minoru Narui, Masanori Yamazaki, Tatsuo T. Shikama, Hideki Matsui

Institute for Materials Research (IMR)

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

4 Citations (Scopus)

Abstract

Fuel claddings of supercritical water-cooled reactor (SCWR) will be used under severe environments such as supercritical water and neutron irradiation. It is one of the key factors to reveal radiation effects on the material performance from the view points of reliability and durability of the fuel claddings. Authors have developed the candidate alloys for the fuel claddings, and investigated radiation effects on them by using specimens irradiated with neutrons up to doses of 5 × 10²⁴ and 1.2 × 10 ²⁶ n/m² (>0.1 MeV) in JMTR and JOYO. As a part of evaluation of neutron irradiation on general corrosion, the alloys, which were irradiated at 600°C, were exposed for over 500 hours in supercritical water at the temperature of 600°C They showed weight change due to oxidation after the exposure, and effects of neutron irradiation on general corrosion of the alloys are discussed from the above results.

Original language	English
Title of host publication	14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Pages	1723-1729
Number of pages	7
Publication status	Published - 2009
Event	714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, VA, United States Duration: 2009 Aug 23 → 2009 Aug 27

Publication series

Name	14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Volume	2

Other

Other	714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Country/Territory	United States
City	Virginia Beach, VA
Period	09/8/23 → 09/8/27

ASJC Scopus subject areas

Nuclear Energy and Engineering
Environmental Engineering

Cite this

Kasahara, S., Kaneda, J., Tsuchiya, Y., Mimura, S., Narui, M., Yamazaki, M., Shikama, T. T., & Matsui, H. (2009). General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor. In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 (pp. 1723-1729). (14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009; Vol. 2).

General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor. / Kasahara, Shigeki; Kaneda, Junya; Tsuchiya, Yumiko et al.

14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009. 2009. p. 1723-1729 (14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009; Vol. 2).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Kasahara, S, Kaneda, J, Tsuchiya, Y, Mimura, S, Narui, M, Yamazaki, M, Shikama, TT & Matsui, H 2009, General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor. in 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009. 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, vol. 2, pp. 1723-1729, 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, Virginia Beach, VA, United States, 09/8/23.

Kasahara S, Kaneda J, Tsuchiya Y, Mimura S, Narui M, Yamazaki M et al. General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor. In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009. 2009. p. 1723-1729. (14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009).

Kasahara, Shigeki ; Kaneda, Junya ; Tsuchiya, Yumiko et al. / General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor. 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009. 2009. pp. 1723-1729 (14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009).

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AU - Narui, Minoru

AU - Yamazaki, Masanori

AU - Shikama, Tatsuo T.

AU - Matsui, Hideki

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AB - Fuel claddings of supercritical water-cooled reactor (SCWR) will be used under severe environments such as supercritical water and neutron irradiation. It is one of the key factors to reveal radiation effects on the material performance from the view points of reliability and durability of the fuel claddings. Authors have developed the candidate alloys for the fuel claddings, and investigated radiation effects on them by using specimens irradiated with neutrons up to doses of 5 × 1024 and 1.2 × 10 26 n/m2 (>0.1 MeV) in JMTR and JOYO. As a part of evaluation of neutron irradiation on general corrosion, the alloys, which were irradiated at 600°C, were exposed for over 500 hours in supercritical water at the temperature of 600°C They showed weight change due to oxidation after the exposure, and effects of neutron irradiation on general corrosion of the alloys are discussed from the above results.

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General corrosion of neutron irradiated candidate alloys for fuel claddings of supercritical water-cooled reactor

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