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Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Ishitsuka, Etsuo; Uchida, Munenori*; Akutsu, Yoichi; Motoki, Ryozo; Watanabe, Wataru; Hirata, Shogo*
JAERI-Tech 2004-036, 138 Pages, 2004/03
JAERI-Tech-2004-036.pdf:4.07MB
This document shows the model case concerned with the utilization of constructed facility for the construction of post irradiation examination facility for fusion blanket. In this report, the radioisotope application and development laboratory is considered as constructed facility for post irradiation examination facility and we planned to improve the radioisotope application and development laboratory to the facility of post irradiation examination for fusion material to reduce the construction fee for this facility and promotion of efficiency by concentration of any equipment for fusion material research.
Kawamura, Hiroshi; Tsuchiya, Kunihiko
FZKA-6720, p.151 - 160, 2002/06
no abstracts in English
O ring irradiated in a fast neutron fluxKurasawa, Toshimasa; O.D.Slagle*; Hollenberg, G. W.*; Verrall, R. A.*
Fusion Technology 1992, p.1404 - 1408, 1993/00
no abstracts in English
Noda, Kenji; Kurasawa, Toshimasa; Watanabe, H.
Adv.Ceram., 25, p.73 - 81, 1989/00
no abstracts in English
O under High Neutron Fluence --- Detritiation and Tritium Monitoring ---; ; Kurasawa, T.; ; ; ; ; ; Naruse, Yuji;
JAERI-M 83-204, 29 Pages, 1983/11
no abstracts in English
Tanigawa, Hisashi; Enoeda, Mikio; Ose, Yasuo*
no journal, ,
For solid breeder blanket, loading of neutron multiplier is required to obtain efficient tritium breeding capability. When Beryllium is used for the multiplier, we have to take care of chemical reaction between Beryllium and water/vapor. Their reaction produces heat and hydrogen potentially leading to excess pressure and/or hydrogen explosion. In this study, thermal-hydraulics behaviour is assessed when the cooling pipe is broken in the blanket module. A two-fluid model calculation code of TRAC-PF1 is used for the analysis. The code was originally developed for fission reactor, and has been modified to study the phenomena in fusion reactor environment. Firstly, transient response in temperature and pressure is analyzed in the conditions expected in ITER-TBM. In this case, effect of heat-transfer enhancement due to ingress of water/vapor is larger than that of chemical reaction. The phenomena in DEMO reactor where the effect of the chemical reaction will be higher than ITER will be discussed.
Ochiai, Kentaro
no journal, ,
It was presented the comprehensive tritium recovery experiment of blanket mock-up assemblies irradiated DT neutron source of JAEA/FNS facility. Especially, the both dependencies of temperature and time response was reported. In addition, based on past result, It was suggested it about simulating blanket irradiation experiment plan by A-FNS which JAEA is planning to construct as next intense neutron source for DEMO reactor and ITER test blanket module.
Tanigawa, Hiroyasu*; Nakajima, Motoki*; Sakasegawa, Hideo; Ando, Masami*; Watanabe, Yoshiyuki*; Nozawa, Takashi*; Kato, Yutai*; Nakata, Toshiya*
no journal, ,