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Osaka, Masahiko; Koi, Mamoru; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*
Journal of Nuclear Science and Technology, 43(4), p.367 - 374, 2006/04
Times Cited Count：12 Percentile：63.1(Nuclear Science & Technology)The low oxygen potential target, which consist of (Th,Am)Ox dispersed in Mo, as a high performance Am-containing target for fast reactors is proposed. Effects of Mo isotopic ratio on the core characteristics are evaluated with various Mos having different isotopic composition.
Koi, Mamoru; Mochizuki, Hiroyasu
JNC TN9200 2004-001, 335 Pages, 2004/06
JNC-TN9200-2004-001.pdf:35.21MB
The O-arai Fast Reactor (FR) cycle symposium 2004 was held on the theme of the direction of the world in FR cycle development and the role of "Joyo" and "Monju" reactors in the O-arai Engineering Center (OEC) on 27 February 2004. Approximately 400 people including municipal people, specialists of FR cycle technology development in Japan and other countries, students, etc attended the symposium.
Koi, Mamoru
Nihon Genshiryoku Gakkai-Shi, 46(9), p.646 - 647, 2004/00
The O-arai Fast Reactor (FR) cycle symposium 2004 was held on the theme of the direction of the world in FR cycle development and the role of "Joyo" and "Monju" reactors in the O-arai Engineering Center (OEC) on 27 February 2004.
Koi, Mamoru
Saikuru Kiko Giho, (23), 88-91 Pages, 2004/00
The O-arai FR Cycle Symposium 2004 was held on the theme of "The direction of the world in FR cycle development and the role of "Joyo" and "Monju" reactors" on 27th February 2004 in O-arai Engineering Center.
Koi, Mamoru
Saikuru Kiko Giho, (20), , 2003/00
Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.
Koi, Mamoru; Chatani, Keiji; Hasegawa, Makoto
Saikuru Kiko Giho, (18), p.94 - 96, 2003/00
The application of the fluoride volatility process in the reprocessing of fuel from the fast breeder reactor is regarded as one of the economical methods. Plutonium hexafluoride (PuF6), however, reacting with fluorine (F2) and plutonium dioxide (PuO2) as the raw material, is in an unstable condition and tends to remain as a solid compound in the process after decomposing into plutonium tetrafluoride (PuF4). Suitable conditions should be established for the practical use of this process. One of them is to enhance the stability of PuF6. The behaviour of plutonium fluorination and relevant chemical reactions were investigated by referring to sundry literature and by thermodynamic calculation. It was then compared with recent data from laboratory scale experiments for this paper. Results from the theoretical analysis agreed with experimental observation that PuF6 could be formed stably under a high temperature condition (approx.1000 K) with over supply of figher concentration of F2.
Watashi, Katsumi; Aoto, Kazumi; Aoki, M; Komine, Ryuji; Ito, Takushi; Hasebe, Shinichi; Kato, Shoichi; Koi, Mamoru; Wada, Yusaku
PNC TN9410 93-142, 120 Pages, 1993/06
Much progress has been made in improving established creep properties of Type 316 stainless steel and to develop a new structural material named "FBR Grade Type 316 Stainless Steel", 316FR, with superior creep properties. This report includes a draft of Material Strength Standard of 316FR and its interpretation on the basis of the major result of research and development conducted so far. The draft includes identical items described in the "Standards for the Strength of Materials" for Monju, and was carefully prepared to have an identical style for convenience in design evaluation. Creep damage evaluation diagrams, which are depicted in the "Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor for Elevated Temperature Service" (ETSDG) for individual materials, are also included in this report.
Koi, Mamoru
PNC TN9410 90-105, 163 Pages, 1990/07
Fatigue and creep crack growth data of SUS304 stainless steel, 2.25Cr-1Mo steel and Mod.9Cr-1Mo steel, which were accumulated in PNC in last several years, were treated as a data base. Average trend equations of crack growth rate were proposed and also statistical analysis was carried out. Finite Elements analysis of center cracked tensioned plate was performed and simplified prediction method of modified J-integral J'(C 
) was developed. 0btained results are summerized as follows: (1)In all tested materials, fatigue crack growth rate and creep crack growth rate were successfully represented using cyclic J-integral range 
J and modified J-integral J', respectivery. (2)In all tested materials, meaningful difference of crack growth rate could not be detected between hot rolled plate and forged material, and also between base metal and welded material. (3)Averaged trend equations of fatigue crack growth rate and creep crack growth rate of all tested materials were proposed on the basis of power low with cyclic J-integral range and modified J-integral, respectively. (4)Assuming that the coefficient and exponent of the above power low obey joint normal distribution, statistical analysis of crack growth rate was carried out and relationship between variance and J, J' were obtained. (5)Simplified method was developed to predict modified J-integral of center cracked tensioned plate. Prediction results show good agreement with experimental results, and this fact suggests that J-integral evaluation method of 3-dimensional surface crack, which has been developed in PNC, has good prediction accuracy.
Koi, Mamoru; Fukui, Yasutaka; Ito, Chikara
no journal, ,
We will report about JAEA's activities of research and development on investigation technology of the PCV and RPV interior, and cutting technology of fuel debris and structures in the reactor for decommissioning of Fukushima-Daiichi NPP.
Matsuo, Mamoru; Ieda, Junichi; Harii, Kazuya; Onuma, Yuichi*; Yokoi, Naoto*; Maekawa, Sadamichi
no journal, ,
no abstracts in English
