Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kawamura, Hiroshi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru; Uchida, Munenori*; Yamada, Hirokazu*; Nakamura, Kazuyuki; Ito, Haruhiko; Nakazawa, Tetsuya; Takahashi, Heishichiro*; et al.
Nuclear Fusion, 43(8), p.675 - 680, 2003/08
Times Cited Count:28 Percentile:63.92(Physics, Fluids & Plasmas)no abstracts in English
Kawamura, Hiroshi; Takahashi, Heishichiro*; Yoshida, Naoaki*; Shestakov, V.*; Ito, Yoshio*; Uchida, Munenori*; Yamada, Hirokazu*; Nakamichi, Masaru; Ishitsuka, Etsuo
Fusion Engineering and Design, 61-62, p.391 - 397, 2002/11
Times Cited Count:40 Percentile:90.08(Nuclear Science & Technology)no abstracts in English
Fujiwara, Masayuki; Mizuta, Shunji;
JNC TN9400 2000-050, 19 Pages, 2000/04
For evaluating the fast reactor system technology, it is important to evaluate the practical feasibility of ODS ferritic cdaddings, which is the most promising matelials to attain the goal of high coolant temperature and more than 150 GWd/t. Based on the results of their technology development, mass production process with highly economically benefit as well as manufacturing cost estimation of ODS ferritic claddings were preliminarily conducted. From the view point of future utility scale, the cost for manufacturig mother tubes has a dominant factor in the total manufacturing cost. The method to reduce the cost of mother tube manufacturing was also preliminarily investigated.
Ishitsuka, Etsuo; Kawamura, Hiroshi
Fusion Engineering and Design, 41, p.195 - 200, 1998/00
Times Cited Count:2 Percentile:24.46(Nuclear Science & Technology)no abstracts in English
Ishitsuka, Etsuo; Kawamura, Hiroshi
Fusion Engineering and Design, 27, p.263 - 268, 1995/00
Times Cited Count:14 Percentile:77.9(Nuclear Science & Technology)no abstracts in English
Tagawa, Hiroaki
Suiso Enerugi Shisutemu No Kaihatsu, p.73 - 125, 1974/00
no abstracts in English
Karyoku Hatsuden, 22(3), p.257 - 264, 1971/03
no abstracts in English
Karyoku Hatsuden, 22(3), p.257 - 264, 1970/00
no abstracts in English
Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori
no journal, ,
Technetium-99m (Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce Mo by (n,) method, a parent nuclide of Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of Mo/Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on Mo/Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO pellets, (2) Separation and concentration of Tc by the solvent extraction from Mo solution, (3) Examination of Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of Mo/Tc production improvement.
Tsuchiya, Kunihiko; Kawamata, Kazuo; Takeuchi, Nobuhiro*; Ishizaki, Hiroyuki*; Niizeki, Tomotake*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Araki, Masanori
no journal, ,
no abstracts in English
Tsuchiya, Kunihiko
no journal, ,
no abstracts in English