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Hamamoto, Shimpei; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Goto, Minoru; Matsuura, Hideaki*; Katayama, Kazunari*; Otsuka, Teppei*; Tobita, Kenji*
Proceedings of 2021 International Congress on Advances in Nuclear Power Plants (ICAPP 2021) (USB Flash Drive), 5 Pages, 2021/10
Impurity concentrations of hydrogen and hydride in the coolant were investigated in detail for the HTTR, a block type high-temperature gas reactor owned by Japan. As a result, it was found that CH
was 1/10 of H
concentration, which was under the conventional detection limit. If the ratio of H to CH in the coolant is the same as the ratio of HT to CH
T, the CHT has a larger dose conversion factor, and this compositional ratio is an important finding for the optimal dose evaluation. Further investigation of the origin of CH suggested that CH was produced as a result of a thermal equilibrium reaction rather than being released as an impurity from the core.
Shimada, Michiya; Hirooka, Yoshihiko*
Nuclear Fusion, 54(12), p.122002_1 - 122002_7, 2014/12
Times Cited Count：39 Percentile：86.11(Physics, Fluids & Plasmas)Tungsten is considered to be the most promising material for divertor in a fusion reactor. Tungsten divertor can withstand the heat loads of ITER, but the heat loads of DEMO divertor is a challenge. Pulsive heat loads as those associated with disruption could melt tungsten targets. The surface would not be flat after subsequent resolidification, which would significantly deteriorate its heat handling capability. Furthermore, DBTT of tungsten is rather high: 
400
C, which would become even higher after neutron irradiation, possibly resulting in cracks in tungsten. Our proposal is to use liquid metal for the divertor target material and actively circulate it with 
force. A simplified analysis of mhd equation in a cylindrical geometry suggests that the engineering requirement is modest. This analysis suggests that this new divertor concept merits further investigation.
Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime
Proceedings of the 1st International Symposium on Advanced Fluid Information (AFI-2001), p.227 - 232, 2001/10
no abstracts in English
Kunugi, Tomoaki; Takase, Kazuyuki; Ogawa, Masuro; Shibata, Mitsuhiko
JAERI-Tech 96-012, 91 Pages, 1996/03
no abstracts in English
laserOka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; Tada, Eisuke; Obara, Kenjiro; ; ; ; Shibanuma, Kiyoshi; Seki, Masahiro
JAERI-Tech 94-033, 20 Pages, 1994/11
no abstracts in English
Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; Tada, Eisuke; Obara, Kenjiro; ; ; ; Shibanuma, Kiyoshi; Seki, Masahiro
JAERI-Tech 94-022, 20 Pages, 1994/10
no abstracts in English
; Ikeda, Yujiro; Kusano, Joichi
JAERI-M 94-016, 89 Pages, 1994/02
no abstracts in English
Japanese Nuclear Data Committee
Nihon Genshiryoku Gakkai-Shi, 33(12), p.1142 - 1150, 1991/12
no abstracts in English
M.Z.Hasan*; Kunugi, Tomoaki
Heat Transfer-Minneapolis,1991 (AIChE Symp. Ser. No. 283), p.67 - 73, 1991/00
no abstracts in English
Japanese Nuclear Data Committee
Nihon Genshiryoku Gakkai-Shi, 32(1), p.56 - 64, 1990/01
no abstracts in English
Ioki, Kimihiro*; ; ; ; ; Abe, Tetsuya; Iida, Hiromasa; Murakami, Yoshio
Fusion Engineering and Design, 10, p.223 - 230, 1989/00
Times Cited Count：5 Percentile：54.89(Nuclear Science & Technology)no abstracts in English
;
Journal of Nuclear Science and Technology, 20(11), p.951 - 960, 1983/00
Times Cited Count：2 Percentile：34.99(Nuclear Science & Technology)no abstracts in English
Furukawa, Kazuo
Kinzoku Butsuri Semina, 6(1), p.11 - 23, 1983/00
no abstracts in English
; ; ; ;
JAERI-M 82-156, 17 Pages, 1982/11
no abstracts in English
;
JAERI-M 82-071, 57 Pages, 1982/07
no abstracts in English
; ; Murakami, Yoshio
Journal of Nuclear Materials, 91(1), p.223 - 226, 1980/00
Times Cited Count：8 Percentile：86.40(Materials Science, Multidisciplinary)no abstracts in English
Furukawa, Kazuo
Nihon Kinzoku Gakkai Kaiho, 19(4), p.225 - 229, 1980/00
no abstracts in English
(flibe) system and its applications; molten slag,molten-salt breeden reactor,fusion reactor,etcFurukawa, Kazuo;
Zairyo Kagaku, 14(6), p.302 - 309, 1977/06
no 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.
