Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Ito, Masayasu; Kawamata, Kazuo; Tayama, Yoshinobu; Kanazawa, Yoshiharu; Yonekawa, Minoru; Nakagawa, Tetsuya; Omi, Masao; Iwamatsu, Shigemi
JAEA-Technology 2011-022, 44 Pages, 2011/07
JAEA-Technology-2011-022.pdf:3.29MB
Hot laboratory are facilities that execute the post irradiation examination of sample irradiated in material testing reactors etc. The handling of high burn-up fuel is scheduled in the JMTR (Japan Materials Testing Reactor) Hot Laboratory with JMTR re-operate in FY 2011. This report describes evaluation, production and installation of shielding of the hot cells in the JMTR Hot Laboratory.
Sozawa, Shizuo; Nakagawa, Tetsuya; Iwamatsu, Shigemi; Hayashi, Koji; Tayama, Yoshinobu; Kawamata, Kazuo; Yonekawa, Minoru; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Omi, Masao
JAEA-Technology 2009-070, 27 Pages, 2010/03
JAEA-Technology-2009-070.pdf:7.46MB
Refurbishment of the Japan Materials Testing Reactor (JMTR), which is recognized as one of important facilities in Japan for safety research, is in progress by the JAEA. In Extensive safety research of light-water reactor (LWR) fuels and materials under a contract with the Nuclear and Industrial Safety Agency of Ministry of Economy, Trade and Industry of Japan, the irradiation tests are planned in order to examine integrity of the LWR fuels and structure materials. For the irradiation tests of high burnup fuels and irradiated materials in the JMTR, modification of the hot laboratory facilities are needed, which are (1) making of application books for strengthening JMTR hot-lab. cell-shielding, (2) the capsule assembling device of detailed design, (3) safety analysis for domestic transportation cask and (4) confirmatory testing of diamond drill of fuel-rod center-hole processing device.
Shibata, Akira; Kawamata, Kazuo; Taguchi, Taketoshi; Kaji, Yoshiyuki; Shimizu, Michio*; Kanazawa, Yoshiharu; Matsui, Yoshinori; Iwamatsu, Shigemi; Sozawa, Shizuo; Tayama, Yoshinobu; et al.
JAEA-Technology 2008-029, 40 Pages, 2008/03
JAEA-Technology-2008-029.pdf:25.78MB
Irradiation assisted stress corrosion cracking (IASCC) is considered to be one of the key issues from a viewpoint of the life management of core components in the aged Light Water Reactors. The in-situ crack extension examination and the in-situ constant load tensile test in the reactor are required for the study of IASCC. There are, however, some technical hurdles to be overcome for the experiments. For this in-situ IASCC test, techniques for assembling pre-irradiated specimens into an capsule in a hot cell by remote handling are necessary. In this report, I describe the establishment of those remote assembling techniques and development of new welding apparatus and the TIG upset welding for stainless tube of 3 mm in thickness. Already IASCC capsules having pre-irradiated CT specimens were remotely assembled using these techniques in the hot cell for performing crack growth tests under irradiation in JMTR. And eight in-situ IASCC capsules have been finished successfully in JMTR.
C in JMTRWakai, Eiichi; Jitsukawa, Shiro; Tomita, Hideki*; Furuya, Kazuyuki; Sato, Michitaka*; Oka, Keiichiro*; Tanaka, Teruyuki*; Takada, Fumiki; Yamamoto, Toshio*; Kato, Yoshiaki; et al.
Journal of Nuclear Materials, 343(1-3), p.285 - 296, 2005/08
Times Cited Count：48 Percentile：93.91(Materials Science, Multidisciplinary)The dependence of helium production on radiation-hardening and -embrittlement has been examined in a reduced-activation martensitic F82H steel doped with 
B, 
B and B+B irradiated at 250C to 2.2 dpa. The total amounts of doping boron were about 60 massppm. The range of He concentration produced in the specimens was from about 5 to about 300 appm. Tensile and fracture toughness tests were performed after neutron irradiation. 50 MeV-He
irradiation was also performed to implant about 85 appm He atoms at 120C by AVF cyclotron to 0.03 dpa, and small punch testing was performed to obtain DBTT. Radiation-hardening of the neutron-irradiated specimens increased slightly with increasing He production. The 100 MPam
DBTT for the F82H+B, F82H+B+B, and F82H+B were 40, 110, and 155C, respectively. The shifts of DBTT due to He production were evaluated as about 70C by 150 appmHe and 115C by 300 appmHe. The DBTT shift in the small punch testing was evaluated as 50C.
pellets and thermocouple re-instrumentation to fuel rod; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.
JAERI-Tech 95-037, 87 Pages, 1995/07
no abstracts in English
fuel particlesMinato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; ; ;
Journal of Nuclear Materials, 208, p.266 - 281, 1994/00
Times Cited Count：43 Percentile：94.61(Materials Science, Multidisciplinary)no abstracts in English
; ; ; ; Kawamura, Hiroshi; ; ; Nakagawa, Tetsuya; ;
JAERI-M 93-206, 48 Pages, 1993/10
no abstracts in English
Tsukada, Takashi; Shiba, Kiyoyuki; Nakajima, Hajime; Usui, Takeshi; Omi, Masao; Goto, Ichiro; ; Nakagawa, Tetsuya; Kawamata, Kazuo; ; et al.
JAERI-M 92-165, 41 Pages, 1992/11
no abstracts in English
Minato, Kazuo; Ogawa, Toru; Kashimura, Satoru; Fukuda, Kosaku; ; ;
J. Mater. Sci., 26, p.2379 - 2388, 1991/00
Times Cited Count：15 Percentile：61.58(Materials Science, Multidisciplinary)no abstracts in English
Minato, Kazuo; Ogawa, Toru; Kashimura, Satoru; Fukuda, Kosaku; ; ;
Journal of Nuclear Materials, 172, p.184 - 196, 1990/00
Times Cited Count：68 Percentile：97.81(Materials Science, Multidisciplinary)no abstracts in English
Minato, Kazuo; Ogawa, Toru; Kashimura, Satoru; Fukuda, Kosaku; ; ;
Journal of Nuclear Materials, 175, p.14 - 19, 1990/00
Times Cited Count：2 Percentile：31.34(Materials Science, Multidisciplinary)no abstracts in English
; ; ; ; ; ; ; ; ; ; et al.
JAERI-M 82-034, 55 Pages, 1982/04
no abstracts in English
Taguchi, Taketoshi; Kato, Yoshiaki; Yonekawa, Minoru; Kanazawa, Yoshiharu; Ito, Masayasu; Kurosawa, Makoto; Aoyagi, Tatsuhiko; Tayama, Yoshinobu; Sozawa, Shizuo; Kawamata, Kazuo
no journal, ,
no abstracts in English
Tayama, Yoshinobu; Kanazawa, Yoshiharu; Souzawa, Shizuo; Kawamata, Kazuo; Shizuoka, Yoshihiro; Onizawa, Satoshi; Nakagawa, Tetsuya
no journal, ,
In the JMTR, the power ramping test is planned with high burn-up fuel as irradiation test. In the hot laboratory facilities, in accordance with the plan, as part of the development of facilities to deal with high burn-up fuel, replacing the assemble method using conventional shielding container, the system was developed that carries capsule to cell and performs assembling using capsule loading system put underwater of canal. Development has been completed in FY 2010.
