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Journal Articles

Next generation reactor development and current status

Kamide, Hideki

Karyoku Genshiryoku Hatsuden, 71(11), p.638 - 648, 2020/11

Development status of next generation reactors is outlined mainly for sodium cooled fast reactor developed in Japan Atomic Energy Agency (JAEA). Development strategy in Japan, status of the advanced reactor developments including SMR over the world, and also results of research and development in JAEA are explained.

Journal Articles

Nuclear fusion reactor

Tobita, Kenji

Karyoku Genshiryoku Hatsuden, 61(10), p.1026 - 1031, 2010/10

https://ci.nii.ac.jp/naid/10027971026

Recent development of fusion reactor technology in Japan is summarized. ITER is a fusion experimental reactor that will play a central role in fusion reactor development in near future. Plasma technology has been focused on exploitation of the ITER operation basis. Long sustainment of high normalized beta discharges performed in JT-60U is a good example of research contributing to ITER. As to fusion engineering, there was remarkable progress in the manufacturing methods of superconducting magnets, and in a high (1 MW), efficient (55%) and long (800 seconds) power generation of 170 GHz radio-frequency waves, which would also contribute to the construction of ITER. The article contains an overview of the Broader Approach program which has been carried out in parallel with the ITER project, as well.

Journal Articles

High-temperature gas-cooled reactor

Hino, Ryutaro; Ogawa, Masuro

Karyoku Genshiryoku Hatsuden, 61(10), p.1032 - 1037, 2010/10

https://ci.nii.ac.jp/naid/10027971037

The goal of broadening industrial applications of nuclear energy while significantly cutting CO $_{2}$ emission can be achieved with the near-term deployable, passively-safe high-temperature gas-cooled reactors (HTGRs), which can supply heat of high-temperatures of up to 950 $^{circ}$ C to a wide range of industrial plants for CO $_{2}$ -free hydrogen production, power generation, etc. This paper introduces technical features of HTGR and the current status of HTGR developments worldwide with emphasis on the R&D activities conducted by Japan Atomic Energy Agency (JAEA). JAEA as the center of excellence on R&D of the HTGR system in Japan, which leads the world R&D on HTGR and nuclear hydrogen production technologies, has successfully carried out the reactor passive safety demonstration and most recently the 50-day high-temperature operation test by using the High Temperature Engineering Test Reactor (HTTR) of 30 MWt. Based on the test results obtained in the HTTR, a commercial power generation system with gas turbine and an advanced system cogenerating electricity by the gas turbine and hydrogen by a thermochemical method have been designed. This paper concludes by giving a perspective of future HTGR developments.

Journal Articles

Risk communication research and practice in Tokai site of Ibaraki

Shobu, Nobuhiro

Karyoku Genshiryoku Hatsuden, 60(4), p.339 - 344, 2009/04

Risk communication activities have been carried out for seven years at Nuclear Fuel Cycle Engineering Laboratories of JAEA. This paper reports on the execution of some specific approaches for risk communication and the outline of the future direction for risk communication to take root in local society.

Journal Articles

Design concept of a knowledge management system of geological disposal technology

Osawa, Hideaki; Umeki, Hiroyuki; Makino, Hitoshi; Takase, Hiroyasu*; McKinley, I. G.*; Okubo, Hiroo*

Karyoku Genshiryoku Hatsuden, 59(6), p.512 - 519, 2008/06

http://ci.nii.ac.jp/naid/10024340318

The information explosion resulting from modern technology is identified as a critical problem for deep geological disposal of high-level radioactive waste (HLW). A paradigm shift is needed in the basic concept for information management. This recognition had led to the development of a next generation Knowledge Management System (the JAEA KMS) that makes maximum use of recent developments in Information Technology (IT) and the methodology of Knowledge Engineering (KE) as applied in other technical fields. This paper provides a brief outline of the design concept of the JAEA KMS and then overviews recent progress towards development of an operational system.

Journal Articles

R&D for tritium removal system using bacteria for safety enhancement of tritium handling in fusion reactor

Hayashi, Takumi; Kobayashi, Kazuhiro; Yamanishi, Toshihiko; Ichimasa, Yusuke*; Ichimasa, Michiko*

Karyoku Genshiryoku Hatsuden, 59(4), p.316 - 321, 2008/04

http://ci.nii.ac.jp/naid/10024193387

In order to enhance safety of fusion reactor, JAEA investigates effective tritium removal system in case of incidental tritium release in the building. Recently, we paid attention to the bacteria, which had an ability of hydrogen oxidation at room temperature, and a new effective detritiation system using the bacteria has been studied under the collaboration with Ibaraki University, instead of catalytic oxidation reactor of rare metal.

Journal Articles

Fast breeder reactor

Sato, Koji

Karyoku Genshiryoku Hatsuden, 58(10), p.1011 - 1028, 2007/10

https://ci.nii.ac.jp/naid/10020087056

Details, current status and future plans for research and development of the fast breeder reactor (FBR) technology in Japan are introduced including a related fuel cycle and an international trend and the international cooperation on FBR cycle technology.

Journal Articles

High-temperature gas-cooled reactors

Ogawa, Masuro; Hino, Ryutaro; Kunitomi, Kazuhiko; Sato, Hiroyuki

Karyoku Genshiryoku Hatsuden, 58(10), p.1029 - 1037, 2007/10

https://ci.nii.ac.jp/naid/10020087076

High temperature gas reactors (HTGRs) are expected to expand the application field of the nuclear energy. This report describes the salient features of the HTGRs such as various heat utilization, excellent safety features, high efficiency, high burn-up, etc. Also, development status of the HTGRs in the world was described.

Journal Articles