Report on the fuel treatment facility operation

Kokusen, Junya; Seki, Masakazu; Abe, Masayuki; Nakazaki, Masato; Kida, Takashi; Umeda, Miki; Kihara, Takehiro; Sugikawa, Susumu

JAERI-Tech 2005-004, 53 Pages, 2005/03

JAERI-Tech-2005-004.pdf:5.92MB

This report presents operating records of dissolution of uranium dioxide and concentration of uranyl nitrate solution and acid removal, which have been performed from 1994 through 2003, for the purpose of feeding 10% and 6% enriched uranyl nitrate solution fuel to Static Experimental Critical Facility(STACY) and Transient Experimental Critical Facility(TRACY) in Nuclear Fuel Safety Engineering Facility(NUCEF).

Electron temperature and density measurements by harmonic electron cyclotron emissions from the doublet-III tokamak plasma

; *; ; *; ; ; ; ; Sengoku, Seio; ; et al.

Physical Review Letters, 55(1), p.83 - 86, 1985/00

https://doi.org/10.1103/PhysRevLett.55.83

no abstracts in English

The JAERI code system for evaluation of BWR ECCS performance

; ; Asahi, Yoshiro; ; ; ;

JAERI 1283, 238 Pages, 1982/12

JAERI-1283.pdf:10.48MB

no abstracts in English

Present status of procurement activities for ITER NB system

Tobari, Hiroyuki; Hanada, Masaya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Dairaku, Masayuki; Yamanaka, Haruhiko; Maejima, Tetsuya; Umeda, Naotaka; Abe, Hiroyuki; Terunuma, Yuto; et al.

no journal, , 

JAEA has started procurement activities for ITER NB test facility (NBTF). NBTF being under construction in Padova, Italy has an objective to establish beam technology for 1 MeV, 40 A D- beam prior to ITER operation. JAEA procures high voltage components of 1 MV power supply such as insulating transformer and HV bushing as insulating feedthrough. Requirements to realize those components exceeds existing technology level, hence JAEA has pushed R&D. As for 1 MV insulating transformer, insulating method with double-walled insulator was newly developed. As for the HV bushing, a new forming method of the world largest ceramic ring and brazing technique were developed, and then a technology that meets ITER requirement has been confirmed. Procurement activities have been started from 2012 and now is undergoing as scheduled. Manufacturing of components will be completed by 2015 and those will be transported and installed in Padova in 2016. Commissioning will start in 2017.

Development of DC ultra-high voltage insulation technology for ITER NBI

Tobari, Hiroyuki; Hanada, Masaya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Kojima, Atsushi; Dairaku, Masayuki; Seki, Norikatsu; Abe, Hiroyuki; Umeda, Naotaka; Yamanaka, Haruhiko; et al.

no journal, , 

https://conferences.iaea.org/indico/contributionDisplay.py?contribId=442&sessionId=31&confId=46

Progress on technical development on ITER and JT-60SA neutral beam injector (NBI) were reported. In development of a 1 MV insulating transformer for ITER NB power supply, a bushing extracting 1 MV required a huge insulator that was impossible to manufacture. To solve this issue, a composite bushing with FRP tube and a small condenser bushing with insulation gas was newly developed. In development the HV bushing as an insulating feed through, voltage holding in large cylindrical electrodes inside the HV bushing was investigated. The scaling for vacuum insulation design of large cylindrical electrodes was obtained. Toward long pulse production and acceleration of negative ion beam, active control system of plasma grid temperature and a new extractor consisting of the extraction grid with high water cooling capability and aperture offset were developed. As a result, 15 negative ion beam has been achieved for 100 s. Also beam energy density has been increased two orders of magnitude.