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Shiroya, Seiji*; Misawa, Tsuyoshi*; Unesaki, Hironobu*; Ichihara, Chihiro*; Kobayashi, Keiji*; Nakamura, Hiroshi*; Shin, Kazuo*; Imanishi, Nobutsugu*; Kanazawa, Satoshi*; Mori, Takamasa
JAERI-Tech 2004-025, 93 Pages, 2004/03
In view of the future plan of Research Reactor Institute, Kyoto University, the present study consisted of (1) the transmission experiments of high energy neutrons through materials, (2) experimental simulation of ADSR using the Kyoto University Critical Assembly(KUCA), and (3) conceptual neutronics design study on KUR type ADSR using the MCNP-X code. Through the present study, valuable knowledge on the basic nuclear characteristics of ADSR, which is indispensable to promote the study on ADSR, was obtained both theoretically and experimentally. For the realization of ADSR, it is considered to be necessary to accumulate results of research steadily. For this purpose, it is inevitable (1) to compile the more precise nuclear data for the wide energy range, (2) to establish experimental techniques for reactor physics study on ADSR including subcriticality measurement and absolute neutron flux measurement, and (3) to develop neutronics calculation tools which take into account the neutron generation process by the spallation reaction and the delayed neutron behavior.
Verzilov, Y. M.; Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo
JAERI-Research 2004-005, 30 Pages, 2004/03
no abstracts in English
Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo
JAERI-Research 2003-019, 25 Pages, 2003/09
no abstracts in English
Okajima, Shigeaki
JAERI-Conf 99-007, p.124 - 127, 1999/07
no abstracts in English
Sekine, Toshiaki
Radioisotopes, 46(9), p.670 - 674, 1997/09
no abstracts in English
Ikeda, Yujiro; D.L.Smith*
Fusion Technology, 30(3(PT.2B)), p.1190 - 1196, 1996/12
no abstracts in English
Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Kosako, Kazuaki*; Maekawa, Hiroshi; Nakamura, Tomoo; M.A.Abdou*; Bennett, E. F.*; A.Kumar*; *; et al.
Fusion Technology, 28(2), p.305 - 319, 1995/09
no abstracts in English
Funahashi, Satoru; Shirai, Eiji; Morii, Yukio; Kodaira, Tsuneo; Takahashi, Hidetake
Journal of Nuclear Science and Technology, 30(8), p.837 - 842, 1993/08
no abstracts in English
; ; *
JAERI-M 82-054, 22 Pages, 1982/06
no abstracts in English
; Akino, Fujiyoshi
Nihon Genshiryoku Gakkai-Shi, 21(11), p.876 - 890, 1979/00
Times Cited Count:1no abstracts in English
;
Journal of Inorganic and Nuclear Chemistry, 40(8), p.1457 - 1460, 1978/08
Times Cited Count:4no abstracts in English
; Akino, Fujiyoshi; ; ; ;
JAERI-M 6549, 59 Pages, 1976/05
no abstracts in English
Kaneko, Yoshihika; Iijima, Tsutomu; Mizuho, Mitsuru; Fuse, Takayoshi*; Fujita, Yoshiaki*; Nakazawa, Masaharu*; Sekiguchi, Akira*; Kimura, Itsuro*
Nihon Genshiryoku Gakkai-Shi, 18(2), p.77 - 88, 1976/02
no abstracts in English
Tone, Tatsuzo
Journal of Nuclear Science and Technology, 12(8), p.467 - 481, 1975/08
Times Cited Count:41no abstracts in English
Ochiai, Kentaro; Edao, Yuki; Kawamura, Yoshinori; Hoshino, Tsuyoshi; Ota, Masayuki; Konno, Chikara
no journal, ,
In order to investigate the tritium recovery property from lithium titanate (LiTiO) pebble, we have carried out the DT neutron irradiation experiment at the Fusion Neutronics Source in Japan Atomic Energy Agency. Especially, we have investigated the influences of the temperature and the water moisture concentration in the sweep gas line on the ratio of the recovered tritium water and tritium gas (HT/HTO). The LiTiO pebbles (67g) put into a stainless steel container was inserted in an experimental assembly fabricated with beryllium and LiTiO blocks. DT neutron irradiation was performed, keeping the temperature of the pebbles uniformly, and recovered on-line the tritium generated within the pebble. The helium gas which contained dry hydrogen gas 1% was mainly used as the sweep gas. The moisture concentration in the helium gas was changed and the collected tritium recovery property for the moisture concentration was also investigated. The HTO and HT collected with water bubblers were measured by the liquid scintillation counter, respectively. From our tritium recovery online experiment, it was shown that the recovered tritium corresponded to the calculated tritium production within the experimental error in the range of 573-1073 K. It was also found that the ratio of the HTO and HT depended on the temperature and the tritium gas recovery was more than 95% at 1073 K.