Development of test techniques for in-pile SCC initiation and growth tests and the current status of in-pile testing at JMTR

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 319-326

  Ugachi, Hirokazu ^a   Kaji, Yoshiyuki ^a   Nakano, Junichi ^a   Matsui, Yoshinori ^a   Kawamata, Kazuo ^a   Tsukada, Takashi ^a   Nagata, Nobuaki ^b   Dozaki, Koji ^b   Takiguchi, Hideki ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Mitoshiro Bldg   (Japan)

Author keywords

Crack monitoring technique; IASCC; In pile testing; JMTR; Load control technique; PIEs; UCL tensile test

Indexed keywords

CRACK INITIATION; CRACK PROPAGATION; HIGH TEMPERATURE OPERATIONS; LIGHT WATER REACTORS; NEUTRON IRRADIATION; STAINLESS STEEL; STRESS ANALYSIS; STRESS CORROSION CRACKING; WATER;

CRACK MONITORING TECHNIQUE; IASCC; IN-PILE TESTING; JMTR; LOAD CONTROL TECHNIQUE; PIES; UCL TENSILE TEST;

NUCLEAR POWER PLANTS;

EID: 33745201379     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (8)

1. Kaji, Y., Tsukada, T., Tsuji, H. and Nakajima, H., 1999, "Development of A Comprehensive Material Performance Database (JMPD) and Analyses of Irradiation Assisted Stress Corrosion Cracking Data", Proc. of 9th Int. Symp. Environmental Degradation of Materials inNuclear Power Systems - Water Reactors, Newport Beach, CA, pp 987-994.
2. Tanigawa, H., Kohyama, A. and Kato, Y., 1996, "A Modeling of Radiation Induced Microstructural Evolution under Applied Stress in Austenitic Alloys", J. Nucl. Mater., 239, pp80-84.
3. Karlsen, T. M. and Hauso, E., "Qualification and Application of Instrumented Specimens for In-Core Studies on Cracking Behavior of Austenitic Stainless Steels", Newport Beach, CA, pp 951-959, 1999
4. Bennet, P. and Karlsen, T. M., "Recent Development in Instrumentation for In-core Materials Degradation Studies in the Halden Reactor", Proc. of 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, in CD-ROM, 2003
5. Tsukada, T., Komori, Y., Tsuji, H., Nakajima, H. and Ito, H., 2002, "New In-Pile Water Loop Facility for IASCC Studies at JMTR", Proc. Int. Conf. Water Chemistry in Nuclear Reactor Systems - Operational Optimization and New Developments (Avignon, France, April 22-26, 2002) Paper No.91.
6. Ugachi, H., Tsukada, T., Matsui, Y., Kaji, Y., Tsuji, H., Nagata, N., Dozaki, K. and Takiguchi, H. "Program of in-pile IASCC testing under the simulated actual plant condition Development of Technique for In-pile IASCC Initiation Test in JMTR - Proc. of 11th International Conference on Nuclear Engineering, 36136, 2003
7. Kaji, Y., Ohmi, M., Matsui, Y., Kita., S., Tsukada, T., Tsuji, H., Nagata, N., Dozaki, K. and Takiguchi, H. "Program of in-pile IASCC testing under the simulated actual plant condition - Development of Technique for In-pile IASCC Initiation Test in JMTR - Proc. of 11th International Conference on Nuclear Engineering, 36119, 2003
8. Katsura, R., Morisawa, J., Kodama, M., Nishimura, S., Suzuki, S., Shima, S. and Yamamoto, M., "Effect of stress on IASCC in irradiated austenitic stainless steels", Proc. of 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors-, pp625-631, 1993