Effect of Dissolved Hydrogen Concentration in Simulated PWR Primary Water on Stress Corrosion Cracking Susceptibility of Ni-based Alloy at 290℃ and 320℃

Author:

KOBAYASHI Takaaki12,YONEZAWA Toshio2,DOZAKI Koji3,HISAMUNE Kenji3,SUGINO Wataru3,SATO Kenji1

Affiliation:

1. Mitsubishi Heavy Industries, Ltd.

2. Tohoku University

3. The Japan Atomic Power Campany

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference20 articles.

1. 1) W. Sugino, “PWR ichiji-kei youzon suiso noudo no saitekika ni kansuru torikumi,” Nihon Genshiryoku Gakkai Mizukagaku Bukai 12kai Kouen, Mar. 7, (2011), [in Japanese].

2. 2) E. J. Hart, W. R. Mcdonel, S. Gordon, “The decomposition of light and heavy water boric acid solution by nuclear reaction radiations,” Proc. Intern. Conf. Peaceful Uses Atomic Energy, Genova, 1955, 7, 593-598 (1956).

3. 3) H. Takiguchi, M. Sekiguchi, H. Christensen, “In-pile loop experiment and model calculations for radiolysis of PWR primary coolant,” Proc. Intern. Conf. Water Chemistry of Nuclear Reactor Systems 8, BNES, Bournemouth, Oct. 22-26, 399 (2000).

4. 4) C. Brun, A. Long, P. Saurin, M. C. Thiry, N. La Coudre, “Radiolysis studies at Belleville (PWR1300) water chemistry with low hydrogen concentration,” Proc. Inter. Conf. On Chemistry in Water Reactors: Operating Experience and New Developments, Nice, 1, 73 (1994).

5. 5) T. Cassage, B. Fleury, F. Vaillant, O. de Bouvier, P. Combrade, “An update on the influence of hydrogen on the PWSCC of nickel base alloys in high temperature water,” Proc. 8th Int. Symp. on Environmental Degradation of Metals in Nuclear Power Systems-Water Reactors, Amelia Island, Aug. (1997).

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