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Wakui, Takashi; Saito, Shigeru; Futakawa, Masatoshi
Materials, 17(23), p.5925_1 - 5925_14, 2024/12
Times Cited Count：0 Percentile：0.00(Chemistry, Physical)The ductile properties of irradiated materials are one of the important indicators related to their structural integrity. Indentation tests are used for evaluating the ductile properties easily and rapidly. Constants in the material constitutive equation were identified via inverse analysis using the Kalman filter, such that the numerical experimental results reproduced the indentation test results. Numerical tensile experiments were conducted using stress-strain curves with the identified constants to obtain nominal stress-strain curves. Furthermore, two methods were proposed for evaluating the total elongation. Evaluated minimum total elongation was 10 %. The evaluation results of ion-irradiated materials were similar to the tensile test results of irradiated materials.
Sugano, Michinaka*; Machiya, Shutaro*; Shobu, Takahisa; Shiro, Ayumi*; Kajiwara, Kentaro*; Nakamoto, Tatsushi*
Superconductor Science and Technology, 33(8), p.085003_1 - 085003_10, 2020/08
Times Cited Count：8 Percentile：41.09(Physics, Applied)Ugachi, Hirokazu; Kaji, Yoshiyuki; Nakano, Junichi*; Matsui, Yoshinori; Kawamata, Kazuo; Tsukada, Takashi; Nagata, Nobuaki*; Dozaki, Koji*; Takiguchi, Hideki*
Proceedings of 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (CD-ROM), p.319 - 325, 2005/00
Irradiation assisted stress corrosion cracking (IASCC) is one of the critical concerns when stainless steel components have been in service in light water reactors (LWRs) for a long period. In the research field of IASCC, mainly PIEs for irradiated materials have been carried out, because there are many difficulties on SCC tests under neutron irradiation. Hence as a part of the key techniques for in-pile SCC tests, we have embarked on a development of the test technique to obtain information concerning effects of applied stress level, water chemistry, irradiation conditions, etc. In this conference, we describe the developed several techniques, especially control of loading on specimens, monitoring technique of crack initiation, propagation and water chemistry, and the current status of in-pile SCC tests using thermally sensitized materials at JMTR.
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
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.
Nakano, Junichi; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Nemoto, Yoshiyuki; Tsuji, Hirokazu; Jitsukawa, Shiro
Journal of Nuclear Materials, 307-311(Part2), p.1568 - 1572, 2002/12
Times Cited Count：13 Percentile：62.54(Materials Science, Multidisciplinary)Type 316LN stainless steel of the international thermonuclear experimental reactor (ITER) Grade (316LN-IG SS) is being considered for the first wall/ blanket component. Hot isostatic pressing (HIP) technique is expected for the fabrication of module. To evaluate the integrity and susceptibility to stress corrosion cracking (SCC) of HIPed 316LN-IG SS, tensile tests in vacuum and slow strain rate tests (SSRT) in high temperature water were performed. Specimen with the HIPed joint shows no deterioration of the tensile strength and susceptibility to SCC in oxygenated water. Thermally sensitized specimen with the HIPed joint was low susceptible to SCC in creviced environment. It is concluded that the strength at joint location is as high as that at the base alloy and the joint interface appears integrity.
Wan, C.*; Kobayashi, Tomokazu*; Motohashi, Yoshinobu*; Sakuma, Takaaki*; Ishihara, Masahiro; Shibata, Taiju
Ibaraki Daigaku Kogakubu Kenkyu Shuho, 49, p.69 - 79, 2002/02
no abstracts in English
Wakai, Eiichi; Hishinuma, Akimichi; Usami, Koji; Kato, Yasushi*; Takaki, Seiichi*; Abiko, Kenji*
Materials Transactions, JIM, 41(9), p.1180 - 1183, 2000/09
no abstracts in English
Tachibana, Yukio; Kojima, Takao; Hanawa, Satoshi; Ishihara, Masahiro
Proceedings of 7th Annual International Conference on Composites Engineering (ICCE-7), p.841 - 842, 2000/00
no abstracts in English
; ; ; Seguchi, Tadao; Yagi, Toshiaki
Proc. of 46th Int. Wire and Cable Symp., p.1 - 5, 1997/00
no abstracts in English
; Ikeda, Shigetoshi*; Seguchi, Tadao; Tabata, Yoneho*
Radiation Physics and Chemistry, 49(2), p.279 - 284, 1997/00
Times Cited Count：98 Percentile：98.20(Chemistry, Physical)no abstracts in English
Matsui, Yoshinori; Hoshiya, Taiji; Jitsukawa, Shiro; Tsukada, Takashi; Omi, Masao; ; Oyamada, Rokuro;
Journal of Nuclear Materials, 233-237, p.188 - 191, 1996/00
Times Cited Count：5 Percentile：44.80(Materials Science, Multidisciplinary)no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Hashimoto, T.*; Kurasawa, Toshimasa; Furuya, Kazuyuki; ; Osaki, Toshio*; Kuroda, Toshimasa*
Journal of Nuclear Materials, 233-237(PT.B), p.940 - 944, 1996/00
Times Cited Count：34 Percentile：91.75(Materials Science, Multidisciplinary)no abstracts in English
Tachibana, Yukio; E.Krempl*
Trans. ASME, Ser. H, 117, p.456 - 461, 1995/10
no abstracts in English
Sato, Kazuyoshi; ; Araki, Masanori; Nakamura, Kazuyuki; Watanabe, Kazuhiro; ; Dairaku, Masayuki; Okumura, Yoshikazu; Ohara, Yoshihiro; Akiba, Masato
16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.220 - 223, 1995/00
no abstracts in English
Kato, Teruo; Maeta, Hiroshi
Teion Kogaku, 30(3), p.143 - 149, 1995/00
no abstracts in English
Jitsukawa, Shiro; Kizaki, Minoru; ; Shiba, Kiyoyuki; Hishinuma, Akimichi
Small Specimen Test Techniques; ASTM STP 1204, p.289 - 307, 1993/00
Times Cited Count：15 Percentile：98.45(Nuclear Science & Technology)no abstracts in English
; Hama, Yoshimasa*; Sasuga, Tsuneo; Seguchi, Tadao
Polymer, 32(14), p.2499 - 2504, 1991/00
Times Cited Count：19 Percentile：67.10(Polymer Science)no abstracts in English
-ray irradiation effects of poly(ethylene-2、6-naphtha late) and poly(ethylene-terephtalate)Saito, Toshio*; Seguchi, Tadao; ;
JAERI-M 89-096, 28 Pages, 1989/08
no abstracts in English
Sasuga, Tsuneo; Hagiwara, Miyuki
Polymer, 27, p.681 - 685, 1986/00
Times Cited Count：12 Percentile：59.19(Polymer Science)no abstracts in English
;
JAERI-M 83-068, 18 Pages, 1983/04
no abstracts in English
