Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kitamura, Akihiro; Nakamichi, Shinya; Kashiro, Kashio
Hoken Butsuri, 47(1), p.66 - 73, 2012/04
Plasma arc cutting is considered to be one of the effective methods to size reduce facility components. This method produces an electrical arc to cut the metal equipment, and during the cutting, a molten metal is ejected in the form of aerosol, which is blown away from the torch and has a potential to spread all over the environment. In order to confirm the safety use of plasma arc cutting for dismantling activity in plutonium fuel fabricating facility, we have performed experiments to find aerosol size distribution and to confirm effectiveness of HEPA filter during the cutting. Results showed that the activity median aerosol diameter was around 6 micrometers, with a geometric standard deviation of 1.9. Also, radiological survey was conducted on the back surface of HEPA filter and confirmed that the penetration of radioactive aerosol was under detection limit.
Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.
JAEA-Technology 2009-072, 144 Pages, 2010/03
JAEA-Technology-2009-072.pdf:45.01MB
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Kitamura, Akihiro; Nakamichi, Shinya; Okada, Takashi
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 7 Pages, 2007/04
Data on glovebox dismantling activities in the Glovebox Dismantling Facility (GDF) were analyzed to identify the work structure and the time consumed for each activity. As a result, we were able to categorize dismantling activities regarding time estimation point of view. The activities those of which variations are around 30% or less, were defined as "predictable activities", and activities those of which total time is small compare to the whole dismantling work were defined as "suppressible activities", and other as "unpredictable activities". In terms of these definition the time interval for unit activity were evaluated and found that almost all of the work can be predicted within 30% uncertainly.
Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Takahashi, Kenji; Ikutama, Shinya*; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji
Nihon Genshiryoku Gakkai-Shi, 48(5), p.333 - 338, 2006/05
no abstracts in English
I using AMS at JAEA-MutsuSuzuki, Takashi; Kitamura, Toshikatsu; Kabuto, Shoji; Isogai, Keisuke*; Bamba, Shigeru*; Katayama, Atsushi; Kameo, Yutaka; Kuwabara, Jun; Sakamoto, Shinya*; Togawa, Orihiko; et al.
no journal, ,
no abstracts in English
Nakamichi, Shinya; Kitamura, Akihiro; Yanagawa, Chihiro; Nakai, Koji; Okada, Takashi; Asazuma, Shinichiro; Kashiro, Kashio
no journal, ,
no abstracts in English
Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Takahashi, Kenji*; Ikutama, Shinya*; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji
no journal, ,
no abstracts in English
Matsui, Yoshinori; Nabeya, Hideaki; Kusunoki, Tsuyoshi; Takahashi, Hiroyuki; Aizawa, Masao; Nakata, Masahito; Numata, Masami; Usami, Koji; Endo, Shinya; Ito, Kazuhiro; et al.
no journal, ,
We are proceeding with the study of "R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant". For the study, it is important that the irradiated specimens are gotten by the coupling of JRR-3 and JOYO. This reports the total irradiation plan in the study, and the executed work for the coupling irradiation (JRR-3 and JOYO) including the Hot facilities work of Tokai and Oarai in the 2006 fiscal year.
Zheng, L.*; Hosoi, Kazuya*; Ueda, Shigeru*; Gao, X.*; Kitamura, Shinya*; Kobayashi, Yoshinao*; Osaka, Masahiko
no journal, ,
Si source for Cs-bearing particle formed by Fukushima-Daiichi NPS accident has yet to be revealed. Stainless steel is possible Si source since it is used as structure material in the reactor and includes Si. In this study, Si vaporization behavior was evaluated by investigation of Si behavior in oxide layer formed in steam atmosphere at 1473 K.
