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Journal Articles

Tensile properties of austenitic stainless steels irradiated at SINQ target 3

Saito, Shigeru; Kikuchi, Kenji; Usami, Koji; Ishikawa, Akiyoshi; Nishino, Yasuharu; Kawai, Masayoshi*; Dai, Y.*

Journal of Nuclear Materials, 343(1-3), p.253 - 261, 2005/08

 Times Cited Count:9 Percentile:55.58(Materials Science, Multidisciplinary)

A beam window of a spallation target will be subjected to proton/neutron irradiation, pressure wave and thermal stresses accompanied by high-energy proton beam injection. To obtain the irradiation data, the SINQ target irradiation program (STIP) was initiated in 1996 at Paul Scherrer Institute (PSI) and has been progressing. JAERI takes part in STIP and shares the PIE work. In this study, the results of tensile tests on austenitic stainless steels, JPCA and 316F SS, will be reported. The results indicate that the irradiation causes considerable hardening and degradation of ductility. The YS increases in this study are slightly large in comparison with those irradiated at fission reactor. Strain-to-necking (STN) values show sufficient large ductility of the irradiated JPCA-SA and 316F-SA. The trends of the STN decrease in this study are slightly abrupt in comparison with those irradiated at fission reactor. All specimens, including irradiated at embrittlement temperature for austenitic steels, fractured in ductile manner.

Journal Articles

Bend-fatigue properties of 590 MeV proton irradiated JPCA and 316F SS

Saito, Shigeru; Kikuchi, Kenji; Usami, Koji; Ishikawa, Akiyoshi; Nishino, Yasuharu; Kawai, Masayoshi*; Dai, Y.*

Journal of Nuclear Materials, 329-333(Part1), p.1093 - 1097, 2004/08

 Times Cited Count:6 Percentile:42.52(Materials Science, Multidisciplinary)

In several institutes, research and development for an accelerator-driven spallation neutron source have been progressed. A beam window of a target will be subjected to proton/neutron irradiation, pressure wave and thermal stresses accompanied by high-energy proton beam injection. To obtain the irradiation data, the SINQ target irradiation program (STIP) at Paul Scherrer Institute (PSI) has been progressing. JAERI takes part in STIP and shares the PIE work. The STIP specimens are very small so that we developed a new fatigue-testing machine with ceramic piezoelectric actuator. The results showed that the numbers of cycles to failure (Nf) on the irradiated specimens were less than that of unirradiated specimens. Dpa dependence of Nf was not clearly seen in the irradiation conditions. On the other hand, fracture surface varied with irradiation conditions. Specimens irradiated at low temperature fractured in ductile manner. However, interglanular fractured surface was observed for 316F SS irradiated up to 12.5 dpa at 360$$^{circ}$$C.

Journal Articles

Post-irradiation tensile and fatigue experiment in JPCA

Kikuchi, Kenji; Saito, Shigeru; Nishino, Yasuharu; Usami, Koji

Proceedings of 6th International Meeting on Nuclear Applications of Accelerator Technology (AccApp '03), p.874 - 880, 2004/00

Specimens irradiated at SINQ were tested by tensile and fatigue. Speciemns were irradiated by 580MeV proton beams under spallation reaction during two years, transported to JAERI and tested at JAERI Hot Cell. Material is JPCA austenitic stainless steel. Strain-to-necking is over 8% at 250$$^{circ}$$C test temperature and are different from APT handbook database. Fatigue test was conducted at low stress regime of high cycle fatigue. The number of cycles to failure is reduced by factors five to ten. These data will help a design of spallation target in JPARC.

Journal Articles

In-situ observation of an austenitic stainless steel weld joint during helium irradiation

Hamada, Shozo; Hojo, Kiichi; Hishinuma, Akimichi

Journal of Nuclear Materials, 205, p.219 - 224, 1993/00

 Times Cited Count:3 Percentile:38.73(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Compositional behavior and stability of MC-type precipitates in JPCA austenitic stainless steel during HFIR irradiation

Suzuki, Masahide; Hamada, Shozo; P.J.Maziasz*; Jitsukawa, Shiro; Hishinuma, Akimichi

Journal of Nuclear Materials, 191-194, p.1351 - 1355, 1992/00

 Times Cited Count:13 Percentile:75.55(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Application of electron energy loss spectroscopy to microchemical analysis of Ti-modified austenitic stainless steel irradiated in HFIR

Hojo, Kiichi; Jitsukawa, Shiro; Suzuki, Masahide; Hamada, Shozo; Hishinuma, Akimichi

Journal of Nuclear Materials, 179-181, p.496 - 499, 1991/00

 Times Cited Count:1 Percentile:20.44(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Microstructural evolution in austenitic stainless steels irradiated to 57 dpa in HFIR

Hamada, Shozo; Suzuki, Masahide; P.J.Maziasz*; Hishinuma, Akimichi

Journal of Nuclear Materials, 179-181, p.515 - 518, 1991/00

 Times Cited Count:7 Percentile:63.72(Materials Science, Multidisciplinary)

no abstracts in English

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