Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Nuclear human resource development using JMTR and related facilities as advanced research infrastructures

Takemoto, Noriyuki; Hori, Naohiko; Nakagawa, Shigeaki; Ishitsuka, Etsuo; Kaminaga, Masanori; Nurzhan, S.*; Takibayev. N.*; Aliyev, B.*; Suzuki, Masahide

Proceedings of International Conference of Young Scientists and Specialists; Current Issues on the Peaceful Use of Atomic Energy (Internet), p.17 - 27, 2012/06

The JMTR is expected to be a key infrastructure with related facilities to contribute the nuclear Human Resource Development (HRD) by a research and On-the-Job-Training (OJT) in order to support global expansion of nuclear power industry. The training program for Asian young researchers and engineers were started from JFY 2011 in JAEA, and 10 trainees from Kazakhstan and Thailand had studied in JFY 2011. In addition, the training course was newly established for domestic students and young engineers from JFY 2010 to JFY 2012, and 45 domestic students and engineers were studied in the course from JFY 2010 to JFY 2011.

Oral presentation

Conceptual design of small-sized high temperature gas-cooled reactor system for electricity generation and district heating

Kasuga, Shoji*; Kubota, Kenichi*; Okamoto, Futoshi*; Maekawa, Isamu*; Furihata, Noboru*; Saito, Masanao*; Kido, Yuji*; Ohashi, Hirofumi; Tachibana, Yukio; Kunitomi, Kazuhiko

no journal, , 

Conceptual design of a small-sized HTGR for electricity generation and district heating has been conducted by JAEA with support of Japanese vendors: Toshiba Corporation, Fuji Electric, Kawasaki Heavy Industries, Nuclear Fuel Industries, Shimizu Corporation, and Marubeni Utility Services. System design as well as nuclear design of the first core of HTR50S using the same CFPs as the HTTR has been performed and the nuclear design shows upgraded performance of the reactor compared with the HTTR.

Oral presentation

Joint experiments for Mo-99 production by (n,$$gamma$$) method

Kimura, Akihiro; Tanimoto, Masataka; Gluschenko, N.*; Morozova, T.*; Moisseikina, N.*; Gurin, A.*; Tsuchiya, Kunihiko; Chakrova, Y.*

no journal, , 

(n,$$gamma$$) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of $$^{99m}$$Tc is remaining as an issue. Therefore, the Poly zirconium compound (PZC) and the $$^{99}$$Mo-Zr gel were developed as Mo absorbent in Japan and Kazakhstan. Then, comparison tests and information exchange were carried out for obtaining specific comparison data of PZC and $$^{99}$$Mo-Zr gel. We were able to obtain specific comparison data of PZC and $$^{99}$$Mo-Zr gel from these experiments.

Oral presentation

Collaboration of JAEA and NNC for Kazakhstan project on high-temperature gas-cooled reactor

Nakatsuka, Toru; Levin, A. G.*; Ueta, Shohei; Gizatulin, S.*; Tachibana, Yukio; Kolodeshnikov, A.*; Sakaba, Nariaki; Chakrov, P.*; Kunitomi, Kazuhiko; Vassiliev, Y. S.*; et al.

no journal, , 

The small-sized high-temperature gas-cooled reactors (HTGRs) with an electric power rating of less than 300 MWe can greatly facilitate decentralized energy supply, and create new industries and stimulate economical development in cities and localities as well as in those remote regions to which power transmission grids are undeveloped in developing countries such as Kazakhstan. In 2007, Japan Atomic Energy Agency (JAEA) and National Nuclear Center of Kazakhstan (NNC) have started to collaborate in nuclear energy research and development for early realization of deployment of the HTGR in Kazakhstan, and to support for the Kazakhstan HTGR (KHTR) Project by utilizing the technologies developed under the High Temperature Engineering Test Reactor (HTTR) Project. In 2010, JAEA started a conceptual design of KHTR steam turbine system with thermal power of 50 MW and the maximum coolant temperature at reactor outlet of 750 $$^{circ}$$C for earlier development of HTGRs with support of Japan parties, which consists of Japanese industrial companies, etc. in order to support NNC for preparation of the feasibility study of KHTR.

4 (Records 1-4 displayed on this page)
  • 1