Experimental study on accelerator driven subcritical reactor, JAERI's nuclear research promotion program, H12-031 (Contract research)

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

JAERI-Tech-2004-025.pdf:6.69MB

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.

Feasibility study of the water cherenkov detector as a D-T fusion power monitor in the system using neutron activation of flowing water; First experimental phase

Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo

JAERI-Research 2003-019, 25 Pages, 2003/09

JAERI-Research-2003-019.pdf:2.42MB

no abstracts in English

Radioisotope production

Sekine, Toshiaki

Radioisotopes, 46(9), p.670 - 674, 1997/09

https://doi.org/10.3769/radioisotopes.46.670

no abstracts in English

Concept and characteristics of a simulated line source for annular blanket experiments using an accelerator-based deuterium-tritium neutron source

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

Comparison of Shielding Capabilities of Fusion Reactor Blanket and Shield Materials

; ; *

JAERI-M 82-054, 22 Pages, 1982/06

JAERI-M-82-054.pdf:0.64MB

no abstracts in English

Yields of Mg in the irradiation of magnesium and aluminium with reactor neutrons

;

Journal of Inorganic and Nuclear Chemistry, 40(8), p.1457 - 1460, 1978/08

https://doi.org/10.1016/0022-1902(78)80451-5

no abstracts in English

Progress in research of reactor neutron spectra

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

https://doi.org/10.3327/jaesj.18.77

no abstracts in English

Study of tritium recovery from lithium titanate pebbles with neutron irradiation

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.