Development of advanced blanket materials for a solid breeder blanket of a fusion reactor

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

https://doi.org/10.1088/0029-5515/43/8/306

no abstracts in English

Evaluation of cost reduction method for manufacturing ODS Ferritic claddings

Fujiwara, Masayuki; Mizuta, Shunji;

JNC TN9400 2000-050, 19 Pages, 2000/04

JNC-TN9400-2000-050.pdf:0.82MB

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.

None

*; *; *; *; *; *; *

PNC TJ9009 96-002, 172 Pages, 1995/10

PNC-TJ9009-96-002.pdf:11.22MB

None

None

PNC TN8420 92-011, 42 Pages, 1992/06

PNC-TN8420-92-011.pdf:1.02MB

None

Present Status of Nuclear Fuel Fabrication Technology in Japan

Karyoku Hatsuden, 22(3), p.257 - 264, 1971/03

https://ci.nii.ac.jp/naid/40017590673

no abstracts in English

Status of Mo/Tc production development by (n,) reaction in JMTR

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.

Status of domestic production of medical radioisotope (technetium-99m) in Japan

Tsuchiya, Kunihiko

no journal, , 

no abstracts in English