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Nakagome, Yoshihiro*; Shimizu, Kenichi
Kaku Busshitsu Kanri Senta Nyusu, 34(2), p.14 - 19, 2005/02
RERTR(Reduced Enrichment for Research and Test Reactors) for 2004 was held at IAEA in Vienna of Austria, An author and Professor Nakagome(Kyoto University) attended this internationalmeeting and the author presented "Status of Reduced Enrichment Program for Research Reactors in Japan" with Dr.Nakagome. JNMCC(Japan Nuclear Material Control Center) requested to present a report of 2004 RERTR international Meeting and related content for the author and Dr.Nakagome. the content of the report described the meeting content and related issue which related US FRR SNF(Foregin Reserach Reactors Spent Nuclear Fuels) Acceptance Program.
Solomon, H. M.*; Kojima, Takuji
Nucleus, 33, p.16 - 20, 2005/00
Low-dose dosimeters were developed based on the mixture films of polyvinyl butyral (PVB) and the acid-sensitive dye leucomalachite green (LMG). Chloral hydrate (RX) was added to the mixture for enhancement of the radiation sensitivity of the film dosimeters. Different film dosimeter materials were prepared using 9.07 
10
mole LMG per one gram PVB with various RX:LMG molar concentration ratio. The dosimeter response, which is expressed in terms of change in absorbance at 628 nm per unit thickness, increased linearly with dose and RX concentration. The PVB-LMG dosimeter system, in which the ratio of RX concentration to that of LMG is higher than 10, show measurable dose range of 1-100 Gy for 
Co 
-rays.
Chihara, Junzo*; Yamagiwa, Mitsuru
Progress of Theoretical Physics, 111(3), p.339 - 359, 2004/03
Times Cited Count：5 Percentile：37.3(Physics, Multidisciplinary)no abstracts in English
Shao, C.*; Furusawa, Yoshiya*; Kobayashi, Yasuhiko; Funayama, Tomoo; Wada, Seiichi
FASEB Journal, 17(11), p.1422 - 1427, 2003/08
Times Cited Count：115 Percentile：87.55(Biochemistry & Molecular Biology)The possible mechanism of a radiation-induced bystander response was investigated by using a high-LET heavy particle microbeam, which allows selected cells to be individually hit with precise numbered particles. Even when only a single cell within the confluent culture was hit by one particle of Ar40 or Ne20, a 1.4-fold increase of micronuclei (MN) was detected demonstrating a bystander response. When 49 cells in the culture were individually hit by 1 to 4 particles, the production of MN in the irradiated cultures were about 2-fold higher than control levels but independent of the number and LET of the particles. MN induction in the irradiated-culture was partly reduced by treatment with DMSO, a scavenger of reactive oxygen species (ROS), and it was almost fully suppressed by the mixture of DMSO and PMA, an inhibitor of gap junctional intercellular communication (GJIC). Accordingly, both ROS and GJIC contribute to the above-mentioned bystander response and GJIC might play an essential role by mediating the release of soluble biochemical factors from targeted cells.
Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Takeda, Takashi*; Fujiki, Kazuo
JAERI-Tech 2002-100, 108 Pages, 2003/01
JAERI-Tech-2002-100.pdf:4.44MB
After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the "improved LEU core" that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle.
Komukai, Bunsaku; Naka, Michihiro; Tabata, Toshio; Nagao, Yoshiharu; Takeda, Takashi*; Fujiki, Kazuo
JAERI-Tech 2002-067, 75 Pages, 2002/08
JAERI-Tech-2002-067.pdf:3.41MB
no abstracts in English
Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nagatomi, Hideki; Kaminaga, Masanori; Funayama, Yoshiro
JAERI-Tech 2002-034, 40 Pages, 2002/03
JAERI-Tech-2002-034.pdf:1.97MB
JRR-4, a swimming-pool type research reactor with a thermal power of 3.5MW, attained criticality in July 1998, after replacing its 90% enrichment fuel with a 20% enrichment fuel under the Reduced Enrichment Program. As a part of the program, safety analysis on thermo-hydraulics of the reactor core was conducted on cases including single channel blockage accident. With the conclusion that a certain margin on thermo-hydraulics was necessary, investigation and experiments were carried out with an aim to increase the core flow rate. To increase the core flow, it was carried out to reduce the bypass flow in the core and to increase the primary coolant flow rate from 7m
/min to 8m/min. After flow measurements using a mock-up fuel element, flow velocity of the fuel channel was determined as 1.45m/s as opposed to the designed value of 1.44m/s, and the ratio of core flow to total flow was 0.88, exceeding the value 0.86 used for the safety analysis.This report describes the JRR-4 core flow increase plan as well as the results of the channel flow rate measurement
Niita, Koji*; Meigo, Shinichiro; Takada, Hiroshi; Ikeda, Yujiro
JAERI-Data/Code 2001-007, 128 Pages, 2001/03
JAERI-Data-Code-2001-007.pdf:5.07MB
no abstracts in English
Naito, Kaoru; Ogawa, Tsuyoshi*; Osabe, Takeshi*
Proceedings of 42nd INMM Annual Meeting, 12 Pages, 2001/00
no abstracts in English
Otsubo, Takashi*; Oya, Susumu*; Goto, Jun*; *; Muto, Suguru*; Osa, Akihiko; Koizumi, Mitsuo; Sekine, Toshiaki
JAERI-Review 99-025, TIARA Annual Report 1998, p.206 - 207, 1999/10
no abstracts in English
Naka, Michihiro; Nagao, Yoshiharu; Komukai, Bunsaku; Tabata, Toshio
Proceedings of 7th Meeting of the International Group on Research Reactors (IGORR-7) (CD-ROM), 7 Pages, 1999/10
no abstracts in English
Watanabe, Shukichi; Nakajima, Teruo; Kaieda, Keisuke
JAERI-Conf 99-006, p.119 - 124, 1999/08
no abstracts in English
Kume, Tamikazu; Matsuhashi, Shimpei; Ito, Hitoshi; Hashimoto, Shoji; *; M.R.Awang*; M.Lebaijuri*; Z.Othman*; F.Ali*; W.B.W.Husain*; et al.
JAERI-Research 98-013, 206 Pages, 1998/03
JAERI-Research-98-013.pdf:9.52MB
no abstracts in English
Takada, Hiroshi; Yoshizawa, Nobuaki*; Kosako, Kazuaki*; *
JAERI-Data/Code 98-005, 101 Pages, 1998/02
JAERI-Data-Code-98-005.pdf:3.57MB
no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi
JAERI-Tech 97-016, 120 Pages, 1997/03
no abstracts in English
Kaminaga, Masanori
JAERI-Tech 97-015, 74 Pages, 1997/03
no abstracts in English
Kaminaga, Masanori
JAERI-Tech 97-014, 125 Pages, 1997/03
no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi
JAERI-Tech 96-039, 72 Pages, 1996/09
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi
Nuclear Science and Engineering, 122, p.212 - 228, 1996/00
Times Cited Count：23 Percentile：85.72(Nuclear Science & Technology)no abstracts in English
Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro
JAERI-Tech 95-040, 79 Pages, 1995/07
no abstracts in English
