Refine your search:     
Report No.
 - 
Search Results: Records 1-10 displayed on this page of 10
  • 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

JAEA Reports

Measurement of pure water resistivity in a high temperature region

Yamanaka, Haruhiko; Maejima, Tetsuya; Terunuma, Yuto; Watanabe, Kazuhiro; Kashiwagi, Mieko; Hanada, Masaya

JAEA-Technology 2014-037, 12 Pages, 2014/12

JAEA-Technology-2014-037.pdf:4.27MB

Resistivity of a high temperature pure water has been measured up to 180$$^{circ}$$C which is the maximum water temperature in the ITER Neutral Beam Injector. The resistivity of the pure water is decreased by increasing the water temperature. It was found that even different resistivity water of 9 M$$Omega$$cm and 5 M$$Omega$$cm showed almost the same resistivity at the higher temperature region of 100$$^{circ}$$C. The resistivity of 0.36 M$$Omega$$cm was measured at the temperature of 180$$^{circ}$$C. This resistivity agreed well to the calculated value for the theoretical pure water.

Journal Articles

Development of negative ion extractor in the high-power and long-pulse negative ion source for fusion application

Kashiwagi, Mieko; Umeda, Naotaka; Tobari, Hiroyuki; Kojima, Atsushi; Yoshida, Masafumi; Taniguchi, Masaki; Dairaku, Masayuki; Maejima, Tetsuya; Yamanaka, Haruhiko; Watanabe, Kazuhiro; et al.

Review of Scientific Instruments, 85(2), p.02B320_1 - 02B320_3, 2014/02

 Times Cited Count:23 Percentile:21.21(Instruments & Instrumentation)

The negative ion extractor for high power and long-pulse operations is newly developed toward the neutral beam injector (NBI) for heating & current drive of future fusion machines such as ITER, JT-60 Super Advanced (SA) and DEMO reactor. The satisfactory cooling capability is designed in the thermal analysis. A negative ion production and a suppression of electrons are experimentally validated for this new extractor. As the results, the negative ion current shows increases by a factor of 1.3 with suppressing the electron current. The beam divergence angle is also maintained small enough, 4 mrad.

Oral presentation

Development of a DC -1 MV insulation transformer for ITER NBI

Watanabe, Kazuhiro; Yamanaka, Haruhiko; Maejima, Tetsuya; Inoue, Takashi; Hanada, Masaya; Tanaka, Shigeru*; Kadowaki, Makoto*

no journal, , 

A DC -1 MV insulation transformer is required for ITER NBI power supply. However such insulation transformer has not been developed. Demonstration of the DC ultra high voltage insulation is essential to realize such insulation transformer. To demonstrate the insulation transformer, a transformer model has been designed and fabricated under the ITER research and development task. The high voltage test with the model has been successfully performed and it ensures that the real insulation transformer can be fabricated.

Oral presentation

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.

Oral presentation

Progress of procurement of the ITER NB power supplies

Yamanaka, Haruhiko; Watanabe, Kazuhiro; Kashiwagi, Mieko; Tobari, Hiroyuki; Maejima, Tetsuya; Hanada, Masaya; Terunuma, Yuto

no journal, , 

A high-energy and high power neutral beam injectors (NBI) of 1 MeV, 16.5 MW neutral power/injector are required for plasma heating and current drive in ITER. A Neutral Beam Test Facility (NBTF), which has the same capacity as the ITER NBI, is constructed at the RFX site in Padua of Italy to demonstrate the specifications and to establish its operation techniques. Capacity of the power supply is DC -1 MV and 60 MW for the beam source with pulse duration up to 3600 s. JAEA as Japan Domestic Agency (JADA) provides ultra-high voltage components of a DC -1 MV power supply for NBTF. To fabricate such UHV NBI power supply components, detailed design has been conducted.

Oral presentation

Progress of procurement of the ITER NB power supplies

Maejima, Tetsuya; Watanabe, Kazuhiro; Kashiwagi, Mieko; Yamanaka, Haruhiko; Terunuma, Yuto; Umeda, Naotaka; Dairaku, Masayuki; Tobari, Hiroyuki; Yamashita, Yasuo*; Shibata, Naoki; et al.

no journal, , 

no abstracts in English

Oral presentation

Experimental study on electrical characteristics of a high temperature pure water for quality improvement of the ITER neutral beam injector power supply

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

no journal, , 

no abstracts in English

Oral presentation

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, , 

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.

Oral presentation

Manufacturing and tests of 1MV power supply for ITER NBTF

Kashiwagi, Mieko; Watanabe, Kazuhiro; Yamanaka, Haruhiko; Maejima, Tetsuya; Terunuma, Yuto*; Oda, Yuki; Tobari, Hiroyuki; Dairaku, Masayuki; Hanada, Masaya

no journal, , 

Toward the neutral beam (NB) system of ITER, the prototype of the ITER NB is under construction in the NB test facility (NBTF), Padova, Italy. For the NBTF, Japan Atomic Energy Agency manufactures, transports and constructs the 1MV high voltage power supply components to generate 1 MV, 60 A for 3600 s, which consist of fourteen components such as five DC generators and transmission lines with 100 m in a length. The manufacturing of the power supply components is in progress as scheduled. Three of five DCGs and 80% of the transmission lines have been completed. In the factory, the voltage holding test including the margin of 20% were successfully demonstrated. Then, these are under transportation to the NBTF. The construction work is started from Dec/2015 as scheduled. As the one of R&Ds results, the development of the water choke made of fiber reinforced plastic (FRP) is reported, which is the alternative of the conventional ceramic.

Oral presentation

Experimental study on electrical characteristics of a high temperature pure water and progress status of the ITER neutral beam injector power supply

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

no journal, , 

no abstracts in English

10 (Records 1-10 displayed on this page)
  • 1