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JAEA Reports

Survey and proposal for Japanese-English bilingual translation of technical terms focusing on nuclear disaster prevention

Togawa, Orihiko; Okuno, Hiroshi

JAEA-Review 2023-043, 94 Pages, 2024/03

JAEA-Review-2023-043.pdf:1.53MB

In order to translate nuclear disaster prevention documents written in Japanese into English, the Basic Act on Disaster Management, the Act on Special Measures Concerning Nuclear Emergency Preparedness, and the Convention on Nuclear Safety were surveyed for corresponding terms in Japanese and English. The survey results were integrated and unified English translations were selected. As a result, a Japanese-English correspondence table of technical terms in the field of nuclear disaster prevention was prepared and proposed.

Journal Articles

Disassembly of JT-60 tokamak device for JT-60SA Project; Disassembly of radioactivated large structures

Okano, Fuminori; Ikeda, Yoshitaka; Sakasai, Akira; Hanada, Masaya; JT-60 Team

Purazuma, Kaku Yugo Gakkai-Shi, 90(10), p.630 - 639, 2014/10

JT-60 tokamak device, as a largest nuclear fusion device in the world, started the experiments since 1985 and had accomplished the research and development of plasma performance toward the DEMO. The project has successfully completed it operation in August 2008 with many results such as accomplishment of break-even plasma condition in 1996. This disassembly was required for JT-60SA project, which is the Satellite Tokamak project under Japan-EU international corroboration to modify the JT-60 to the superconducting tokamak. This work was the first experience of disassembling a large radioactive fusion device based on Radiation Hazard Prevention Act in Japan. This report presents the outline of disassembly of JT-60 tokamak device.

Journal Articles

Development and operation of the JAERI superconducting energy recovery linacs

Minehara, Eisuke

Nuclear Instruments and Methods in Physics Research A, 557(1), p.16 - 22, 2006/02

 Times Cited Count:11 Percentile:60.11(Instruments & Instrumentation)

The JAERI FEL facility at Tokai, Ibaraki, Japan has been well known one of the two existing and operating superconducting energy recovery linacs together with one more of JLAB (Jefferson national accelerator facility) FEL facility at Newport News, Virginia, U.S.A. We have independently and successfully developed one of the most advanced and newest accelerator technologies named "superconducting energy recovery linacs (ERLs)" and the application technologies using ERLs in future. We plan to report the current high power FEL upgrade program research, stress corrosion cracking prevention technology research, large current and high brightness photoelectron gun research of negative-electron affinity (NEA) photocathode and NEA electron-excitation cathode as the most important elemental technology in realizing many powerful ERLs.

Journal Articles

JAERI 10kW high power ERL-FEL and its applications in nuclear energy industries

Minehara, Eisuke; Hajima, Ryoichi; Iijima, Hokuto; Kikuzawa, Nobuhiro; Nagai, Ryoji; Nishimori, Nobuyuki; Nishitani, Tomohiro; Sawamura, Masaru; Yamauchi, Toshihiko

Proceedings of 27th International Free Electron Laser Conference (FEL 2005) (CD-ROM), p.305 - 308, 2005/00

The JAERI high power ERL-FEL has been extended to the more powerful and efficient free-electron laser (FEL) than 10kW for nuclear energy industries, and other heavy industries like defense, shipbuilding, chemical industries, environmental sciences, space-debris, and power beaming and so on. In order to realize such a tunable, highly-efficient, high average power, high peak power and ultra-short pulse FEL, we need the efficient and powerful FEL driven by the JAERI compact, stand-alone and zero boil-off super-conducting RF linac with an energy-recovery geometry. Our discussions on the ERL-FEL will cover the current status of the 10kW upgrading and its applications of non-thermal peeling, cutting, and drilling to decommission the nuclear power plants, and to demonstrate successfully the proof of principle prevention of cold-worked stress-corrosion cracking failures in nuclear power reactors under routine operation using small cubic low-Carbon stainless steel samples.

JAEA Reports

Study on the safety system in the High Temperature Gas Cooled Reactor (Contract research)

Nishihara, Tetsuo; Muto, Yasushi; Uchida, Shoji*; Yoshioka, Naoki*

JAERI-Tech 2001-077, 44 Pages, 2001/12

JAERI-Tech-2001-077.pdf:2.16MB

JAERI has conducted the feasibility study of the HTGR gas turbine system from 1996 to 2000 sponsored by MEXT. This report concludes the safety criteria and rationalization of the safety items in the HTGR system.With respect to the safety criteria, the same value for the LWR is selected as the limit of radiation exposure. Probability of the design basis event (DBE) and beyond design basis event (BDBE) is set lower than those for the LWR to get higher safety margin. Adequate initial events and mitigation system are selected to consider the event sequence. The concept of the probability analysis is applied to identify DBEs and BDBEs. It is found that some safety items can be rationalized in consideration of the safety features of the HTGR. Finally, the safety class and design category of the items in the HGTR-GT are classified.

JAEA Reports

R&D on seismic emergency information system

Seismic Emergency Information System Research Team

JAERI-Tech 2001-036, 294 Pages, 2001/06

JAERI-Tech-2001-036.pdf:23.23MB

no abstracts in English

JAEA Reports

Status of nuclear safety research, 2000

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2000-028, 106 Pages, 2000/11

JAERI-Review-2000-028.pdf:14.37MB

no abstracts in English

Journal Articles

Radiological emergency preparedness in Japan

Yamamoto, Hideaki

Proc. of IAEA/KINS Nuclear Safety Symp., 0, p.26 - 31, 1996/00

no abstracts in English

Journal Articles

Recent development and results from severe accident research in Japan

Soda, Kunihisa; Sugimoto, Jun; Yamano, N.; Shiba, Koreyuki

NUREG/CP-0118, p.12-7 - 12-8, 1991/00

no abstracts in English

Oral presentation

Technical issues for safety improvement, 1; Core damage prevention in case of accidents

Nishi, Yoshihisa*; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Yamada, Hidetomo*; Nakamura, Hideo

no journal, , 

no abstracts in English

10 (Records 1-10 displayed on this page)
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