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Kawamata, Kazuo; Nakagawa, Tetsuya; Omi, Masao; Hayashi, Koji; Shibata, Akira; Saito, Junichi; Niimi, Motoji
JAEA-Conf 2008-011, p.78 - 86, 2009/01
The JMTR-HL was founded to examine the objects mainly irradiated in the JMTR in 1971. The JMTR-HL has an advantage that the hot cell is connected with the reactor vessel of the JMTR by a canal. Hence it is easy to transport irradiated radioactive capsules and specimens through the canal. Since 1971, about 2,400 irradiated capsules have been treated in the JMTR-HL and various PIEs have been widely performed there. In recent years, several new techniques, e.g., an in-cell IASCC test, a scanning-electron microscope (SEM) / electron-back scattering-diffraction pattern (EBSD) observation, were added to the conventional PIEs. In addition, the JMTR-HL had contributed to realize an in-pile IASCC test program at the JMTR through the development of a TIG welding technique by remote-handling with manipulators in the hot cell for re-assembling of capsules. A modification of the facility to treat high burn-up fuels, up to about 100 GWD/t, is planned at the JMTR-HL now.
Shibata, Akira; Nakano, Junichi; Omi, Masao; Kawamata, Kazuo; Saito, Takashi; Hayashi, Koji; Saito, Junichi; Nakagawa, Tetsuya; Tsukada, Takashi
Proceedings of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), 8 Pages, 2008/05
Irradiation assisted stress corrosion cracking (IASCC) is considered to be one of the key issues in the aged Light Water Reactors. To simulate IASCC behavior by the in-pile or post-irradiation experiment, it is necessary to irradiate specimens up to a neutron fluence that is higher than the so-called IASCC threshold fluence. There are, however, some technical hurdles to be overcome for the experiments. The techniques assembling pre-irradiated specimens into a in-pile test capsule in a hot cell and the eveluation of material integrity of the capsule during a long term irradiation are necessary. To evaluate material integrity on capsules during a long term irradiation, tensile test and SSRT using specimens which was previously irradiated to 1.0
3.9
10
n/m
were performed. In this paper, technical developments required for IASCC test, e.g. the development of assembling techniques for IASCC capsules and the evaluation of stainless steels which dosed high-fluence neutron were described.
Kawamata, Kazuo; Ishii, Toshimitsu; Kanazawa, Yoshiharu; Iwamatsu, Shigemi; Omi, Masao; Shimizu, Michio; Matsui, Yoshinori; Ugachi, Hirokazu; Kaji, Yoshiyuki; Tsukada, Takashi; et al.
JAEA-Conf 2006-003, p.115 - 125, 2006/05
no abstracts in English
Matsui, Yoshinori; Hanawa, Satoshi; Ide, Hiroshi; Tobita, Masahiro*; Hosokawa, Jinsaku; Onuma, Yuichi; Kawamata, Kazuo; Kanazawa, Yoshiharu; Iwamatsu, Shigemi; Saito, Junichi; et al.
JAEA-Conf 2006-003, p.105 - 114, 2006/05
Irradiation assisted stress corrosion cracking (IASCC) caused by the simultaneous effects of radiation, stress and high temperature water environment is considered to be one of the critical concerns of in-core structural materials not only for light water reactors (LWRs) but also for water-cooled fusion reactors. In the research field of IASCC, post-irradiation examinations (PIEs) for irradiated materials have been mainly carried out, because there are many difficulties on SCC tests under neutron irradiation environment. Hence we have embarked on a development of the test techniques for performing the in-pile SCC tests. In this paper, we describe the developed several in-pile test techniques and the current status of in-pile SCC tests at Japan Materials Testing Reactor (JMTR).
Hanawa, Satoshi; Ogiyanagi, Jin; Mori, Yuichiro*; Saito, Junichi; Tsukada, Takashi
JAEA-Conf 2006-003, p.350 - 357, 2006/05
no abstracts in English
Hoshiya, Taiji; Ueno, Fumiyoshi*; Takaya, Shigeru; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Aoto, Kazumi; Tsukada, Takashi*; Abe, Yasuhiro; Nakamura, Yasuo; et al.
JNC TY9400 2004-026, 53 Pages, 2004/10
JNC-TY9400-2004-026.pdf:22.07MB
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.
Hoshiya, Taiji*; Ueno, Fumiyoshi; Takaya, Shigeru*; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Aoto, Kazumi*; Tsukada, Takashi; Abe, Yasuhiro*; Nakamura, Yasuo*; et al.
JAERI-Research 2004-016, 53 Pages, 2004/10
JAERI-Research-2004-016.pdf:22.07MB
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.
Ishii, Toshimitsu; Ooka, Norikazu; Hoshiya, Taiji; Kobayashi, Hideo*; Saito, Junichi; Niimi, Motoji; Tsuji, Hirokazu
Journal of Nuclear Materials, 307-311(Part.1), p.240 - 244, 2002/12
Times Cited Count：3 Percentile：23.41(Materials Science, Multidisciplinary)no abstracts in English
Ishii, Toshimitsu; Yonekawa, Minoru; Omi, Masao; Takada, Fumiki; Saito, Junichi; Ioka, Ikuo; Miwa, Yukio
KAERI/GP-192/2002, p.157 - 166, 2002/00
no abstracts in English
Saito, Junichi; Ishii, Toshimitsu; Omi, Masao; Fujiki, Kazuo; Ito, Haruhiko; Takahashi, Hidetake
KAERI/GP-192/2002, p.3 - 11, 2002/00
no abstracts in English
Ishii, Toshimitsu; Ooka, Norikazu; Naka, Michihiro; Kanaya, Kunio; Saito, Junichi; Okamoto, Yoshizo*
Proceedings of 6th Far-East Conference on Nondestructive Testing (FENDT '02), p.273 - 278, 2002/00
no abstracts in English
Ishii, Toshimitsu; Omi, Masao; Saito, Junichi; Hoshiya, Taiji; Ooka, Norikazu; Jitsukawa, Shiro; Eto, Motokuni
Journal of Nuclear Materials, 283-287(Part.2), p.1023 - 1027, 2000/12
Times Cited Count：12 Percentile：62.16(Materials Science, Multidisciplinary)no abstracts in English
; Ooka, Norikazu; ; Saito, Junichi; Hoshiya, Taiji; *; Kobayashi, Hideo*
JAERI-Conf 99-009, p.163 - 172, 1999/09
no abstracts in English
Omi, Masao; Saito, Junichi; ; Hoshiya, Taiji; Jitsukawa, Shiro
JAERI-Conf 99-009, p.151 - 162, 1999/09
no abstracts in English
Ishii, Toshimitsu; Ooka, Norikazu; Saito, Junichi; Kobayashi, Shunichi; Takahashi, Kunihiro; Tsukada, Takashi; Iwai, Takashi; Kurosawa, Yoshiaki; Hoshiya, Taiji; Tsuji, Hirokazu
Proceedings of International Symposium on Case Histories on Integrity and Failures in Industry (CHIFI), p.227 - 236, 1999/00
no abstracts in English
*; Endo, Yasuichi; Yamaura, Takayuki; Hoshiya, Taiji; Niimi, Motoji; Saito, Junichi; ; Ooka, Norikazu; Kobiyama, M.*
Journal of Nuclear Materials, 258-263, p.2041 - 2045, 1998/00
Times Cited Count：6 Percentile：49.22(Materials Science, Multidisciplinary)no abstracts in English
*; Endo, Yasuichi; Yamaura, Takayuki; Niimi, Motoji; Hoshiya, Taiji; Saito, Junichi; ; Ooka, Norikazu; *
JAERI-Research 97-028, 46 Pages, 1997/03
JAERI-Research-97-028.pdf:2.49MB
no abstracts in English
Omi, Masao; Saito, Junichi; Ooka, Norikazu; Jitsukawa, Shiro; Hishinuma, Akimichi;
Nihon Genshiryoku Gakkai-Shi, 39(11), p.966 - 974, 1997/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Saito, Junichi; Hoshiya, Taiji; ;
JAERI-Tech 96-015, 58 Pages, 1996/03
no abstracts in English
Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;
JAERI-Tech 96-005, 39 Pages, 1996/02
no abstracts in English
