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Takemoto, Noriyuki; Kimura, Nobuaki; Ooka, Makoto
UTNL-R-0483, p.10_1_1 - 10_1_10, 2013/03
no abstracts in English
Kusunoki, Hidehiko; Oto, Tsutomu; Asano, Norikazu; Hanakawa, Hiroki
UTNL-R-0483, p.10_7_1 - 10_7_9, 2013/03
no abstracts in English
Kameyama, Yasuhiko; Onoue, Ryuji; Hanawa, Yoshio; Nemoto, Nobuaki
UTNL-R-0483, p.10_6_1 - 10_6_6, 2013/03
no abstracts in English
Imaizumi, Tomomi; Ide, Hiroshi; Naka, Michihiro; Komukai, Bunsaku; Nagao, Yoshiharu
UTNL-R-0483, p.10_2_1 - 10_2_8, 2013/03
no abstracts in English
Nagata, Hiroshi; Yamaura, Takayuki; Nagao, Yoshiharu
UTNL-R-0483, p.10_3_1 - 10_3_9, 2013/03
no abstracts in English
MoTaguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo
UTNL-R-0483, p.10_5_1 - 10_5_13, 2013/03
JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of Mo, we have been conducting research and development that can contribute to supply about 25% for Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of Mo: Maintenance of test equipment in the facility in JMTR Hot Laboratory in preparation for research and development for the production of Mo in JMTR and using MoO
pellet irradiated at Kyoto University Research Reactor Institute (KUR).
Ito, Hideaki; Ashida, Takashi; Takamatsu, Misao
UTNL-R-0483, p.6_1 - 6_10, 2013/03
no abstracts in English
Sumino, Kozo; Suto, Masayoshi; Tanaka, Akihiro
UTNL-R-0483, p.7_1 - 7_10, 2013/03
no abstracts in English
Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Omi, Masao
UTNL-R-0483, p.10_4_1 - 10_4_10, 2013/03
In JAEA(Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR. (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation.
Takada, Shoji; Yanagi, Shunki; Iigaki, Kazuhiko; Shinohara, Masanori; Tochio, Daisuke; Shimazaki, Yosuke; Ono, Masato; Sawa, Kazuhiro
UTNL-R-0483, p.9_1 - 9_10, 2013/03
no abstracts in English