Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Nagata, Hiroshi; Kochiyama, Mami; Chinone, Marina; Sugaya, Naoto; Nishimura, Arashi; Ishikawa, Joji; Sakai, Akihiro; Ide, Hiroshi
JAEA-Data/Code 2024-016, 44 Pages, 2025/03
JAEA-Data-Code-2024-016.pdf:3.54MB
The elemental composition of the structural materials of nuclear reactor facilities is used as one of the important parameters in activation calculations that are evaluated when formulating decommissioning plans. Regarding the elemental composition of aluminum alloys and other materials used as structural materials for test and research reactors, sufficient data is not available regarding elements other than the major elements. For this reason, samples were collected from aluminum alloy, beryllium, hafnium, and other materials that have been used as the main structural materials of JMTR (Japan Materials Testing Reactor), and their elemental compositions were analyzed. This report summarizes the elemental composition data of 78 elements obtained in FY2023.
Owada, Mitsuhiro; Nakanishi, Yoshiki; Murokawa, Toshihiro; Togashi, Kota; Saito, Katsunori; Nonaka, Kazuharu; Sasaki, Yu; Omori, Koji; Chinone, Makoto; Yasu, Hideto; et al.
JAEA-Technology 2024-013, 221 Pages, 2025/02
JAEA-Technology-2024-013.pdf:14.98MB
The uranium enrichment facilities at the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency (JAEA) were constructed sequentially to develop uranium enrichment technology with centrifugal separation method. The developed technologies were transferred to Japan Nuclear Fuel Limited until 2001. And the original purpose has been achieved. Wastewater Treatment Facility, one of the uranium enrichment facilities, was constructed in 1976 to treat radioactive liquid waste generated at the facilities, and it finished the role in 2008. In accordance with the Medium/Long-Term Management Plan of JAEA Facilities, interior equipment installed in this facility had been dismantled and removed since November 2021 to August 2023. This report summarizes the findings obtained through the work related to dismantling and removal of interior equipment for decommissioning of Wastewater Treatment Facility.
Kitamura, Satomi*; Chinone, Shumpei*; Tokuhiro, Koji*; Nakatsubo, Koichi*; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 64, 2011/01
no abstracts in English
Takeuchi, Shinji; Chinone, Tatsuya*; Mebruck, N.*; Watanabe, Kunio*
Sui Kogaku Rombunshu (CD-ROM), 54, p.409 - 414, 2010/02
Tunnel or shaft excavation in fractured rock mass brings out the pore pressure change around the site. The effect of the construction is spatially different due to the existence of high permeable fractures around the site. The precise prediction with real time of pore pressure change is very important to maintain the groundwater in good condition. In this paper, pore pressure measured by 50 sensors which was installed in 5 boreholes around two shafts that are now under construction for Mizunami underground research laboratory project of JAEA, was analysed by using Genetic Algorithm (GA) and Artificial Neural Network (ANN). It was found that the pore pressure change in this area could be divided into four patterns. The pore pressure fluctuation at an arbitrary point was precisely predicted on real time with pore pressure data obtained at other sections when the fluctuation patterns of those data are identical.
"Momoka"Chinone, Shumpei*; Tokuhiro, Koji*; Nakatsubo, Koichi*; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2009-041, JAEA Takasaki Annual Report 2008, P. 74, 2009/12
no abstracts in English
and 
irradiated with ion beamsChinone, Shumpei*; Tokuhiro, Koji*; Nakatsubo, Koichi*; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2008-055, JAEA Takasaki Annual Report 2007, P. 68, 2008/11
no abstracts in English
Chinone, Shumpei*; Ishizawa, Akito*; Tokuhiro, Koji*; Nakatsubo, Koichi*; Amano, Masayuki*; Hase, Yoshihiro; Narumi, Issei; Tanaka, Atsushi
JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 83, 2008/03
no abstracts in English
Chinone, Shumpei*; Hanaoka, Yasushi*; Tokuhiro, Koji*; Nakatsubo, Koichi*; Amano, Masayuki*; Hase, Yoshihiro; Tanaka, Atsushi; Narumi, Issei
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 90, 2007/02
no abstracts in English
none*
JNC TN1340 2005-002, 146 Pages, 2005/09
JNC-TN1340-2005-002.pdf:10.68MB
None
Wada, Yusaku; Okubo, Toshiyuki; Miyazaki, Hitoshi; none; Donomae, Yasushi
JNC TN9410 2005-007, 94 Pages, 2005/03
JNC-TN9410-2005-007.pdf:6.07MB
None
none
JNC TN9410 2004-019, 26 Pages, 2005/01
JNC-TN9410-2004-019.pdf:1.92MB
The reactor safety committee chairman of O-arai Engineering Center submitted review principles for the JOYO secondary pipe thickness maintenance condition, reflecting the secondary pipe break accident of Mihama power station No.3 of Kansai Electric Power Cooperation (9th. August 2004), A Specialist review committee for the JOYO secondary pipe thickness maintenance condition was established on 17th. August 2004. According the principles, the specialist committee reviewed following items based on explanations and documents of the Experimental Reactor Division, (1)Maintenance method of the secondary pipe thickness. (2)Maintenance and inspection results of the secondary-pipe thickness. Erosion-corrosion at inner wall of the JOYO secondary cooling loop pipe can hardly occur by the repetition of oxide formation, growth and peeling occurring in water environment, because the coolant of JOYO is not water but sodium. The maximum material loss in the secondary pipe is supposed to occur at the outer-surface of heat-transfer-pipe in the main air coolers due to contact of circulating air. Therefore, this committee paid attention to this portion for reviews. It was confirmed by the operator (Experimental Reactor Division) in periodical independent inspections that heat-transfer-pipe thickness was still larger than the minimum design value. Based on the carried review, the specialist committee has reported to the reactor safety committee that the maintenance method ((1)) was appropriate and the maintenance condition and inspection ((2)) were well for the secondary pipe.
None*
JNC TN1200 2003-006, 224 Pages, 2003/12
JNC-TN1200-2003-006.pdf:11.71MB
This Report is a Proceeding of the Fourth Review Meeting for the JNC International Fellowship Program, held on October 17th, 2003, at Tokai. The report contains 9 presentations of the research works performed by fellows currently invited to JNC.
Suzuki, Junichi; Kadowaki, Kazuo; Hata, Yoshiaki*; Okayasu, Satoru; Nishio, Taichiro; Kakeya, Itsuhiro*; Odawara, Akikazu*; Nagata, Atsushi*; Nakayama, Satoshi*; Chinone, Kazuo*
Teion Kogaku, 38(9), p.485 - 492, 2003/09
no abstracts in English
none*
JNC TN1400 2003-009, 196 Pages, 2003/08
JNC-TN1400-2003-009.pdf:13.97MB
The Japan Nuclear Cycle Development Institute (JNC) commenced a JNC Postdoctoral Fellowship Program in 1997 in order to raise capable researchers by providing an appropriate research environment to young postdoctoral researchers, which means that fiscal year 2002 was the sixth year of the program. The purpose of this program is to provide young researchers full of originality with opportunities to perform research independently on themes related to leading research, and basic and fundamental research of JNC, selected by the researchers themselves and approved by JNC, for a period of two or three years and also to promote the efficiency of JNC's research. This report includes a summary of the results of the research on sixteen themes performed by JNC Postdoctoral Fellows in the fiscal year 2002. Of these, research into four themes ended in 2002.
none*
JNC TN1400 2003-008, 216 Pages, 2003/08
JNC-TN1400-2003-008.pdf:13.92MB
The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (C) on the Nuclear Fuel Cycle in 1999 in order to promote research collaboration with universities and other research institutes (referred to as "universities, etc." below), which means that the fiscal year 2002 was the fourth year of the scheme. This scheme is to invite foresighted and original themes of basic and fundamental research, to be performed using JNC's facilities and equipment, in principle, for the research and development of JNC in the field of the nuclear fuel cycle, from researchers at universities, etc. Those researchers who propose research themes in response to the invitation are expected to lead the research. The purpose of the scheme is to promote the efficiency of basic and fundamental research and development by enhancing the research environment of JNC through collaboration between JNC's own researchers and other researchers, and exchange of information and ---
none*
JNC TN1400 2003-007, 289 Pages, 2003/08
JNC-TN1400-2003-007.pdf:18.64MB
The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as "universities, etc." below), which means that the fiscal year 2002 was the eighth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects of JNC through collaboration with universities, etc. by using mainly JNC's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JNC as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JNC screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JNC. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2002 on 42 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2002. Of these, five were related to fast breeder reactors, three to the nuclear fuel cycle, one to radiation safety and three to geological disposal/ geoscience.
hydrate; Synthesis, composition, structure, dissociation behavior, and a comparison to structure I CH
hydrateCircone, S.*; Stern, L. A.*; Kirby, S. H.*; Durham, W. B.*; Chakoumakos, B. C.*; Rawn, C. J.*; Rondinone, A. J.*; Ishii, Yoshinobu
Journal of Physical Chemistry B, 107(23), p.5529 - 5539, 2003/06
Times Cited Count：190 Percentile：95.84(Chemistry, Physical)no abstracts in English
Rondinone, A. J.*; Chakoumakos, B. C.*; Rawn, C. J.*; Ishii, Yoshinobu
Journal of Physical Chemistry B, 107(25), p.6046 - 6050, 2003/06
Times Cited Count：21 Percentile：48.62(Chemistry, Physical)no abstracts in English
Hata, Yoshiaki; Suzuki, Junichi; Kakeya, Itsuhiro*; Kadowaki, Kazuo*; Odawara, Akikazu*; Nagata, Atsushi*; Nakayama, Satoshi*; Chinone, Kazuo*
Physica C, 388-389(1-4), p.719 - 720, 2003/05
no abstracts in English
None; Koakutsu, Masayuki; Nakazawa, Osamu; Suguro, Toshiyasu; Kato, Hiroshi
Saikuru Kiko Giho, (21), P. 126, 2003/00
None
