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Journal Articles

22A beam production of the uniform negative ions in the JT-60 negative ion source

Yoshida, Masafumi; Hanada, Masaya; Kojima, Atsushi; Kashiwagi, Mieko; Grisham, L. R.*; Hatayama, Akiyoshi*; Shibata, Takanori*; Yamamoto, Takashi*; Akino, Noboru; Endo, Yasuei; et al.

Fusion Engineering and Design, 96-97, p.616 - 619, 2015/10

 Times Cited Count:11 Percentile:67.3(Nuclear Science & Technology)

In JT-60 Super Advanced for the fusion experiment, 22A, 100s negative ions are designed to be extracted from the world largest ion extraction area of 450 mm $$times$$ 1100 mm. One of the key issues for producing such as high current beams is to improve non-uniform production of the negative ions. In order to improve the uniformity of the negative ions, a tent-shaped magnetic filter has newly been developed and tested for JT-60SA negative ion source. The original tent-shaped filter significantly improved the logitudunal uniformity of the extracted H$$^{-}$$ ion beams. The logitudinal uniform areas within a $$pm$$10 deviation of the beam intensity were improved from 45% to 70% of the ion extraction area. However, this improvement degrades a horizontal uniformity. For this, the uniform areas was no more than 55% of the total ion extraction area. In order to improve the horizontal uniformity, the filter strength has been reduced from 660 Gasus$$cdot$$cm to 400 Gasus$$cdot$$cm. This reduction improved the horizontal uniform area from 75% to 90% without degrading the logitudinal uniformity. This resulted in the improvement of the uniform area from 45% of the total ion extraction areas. This improvement of the uniform area leads to the production of a 22A H$$^{-}$$ ion beam from 450 mm $$times$$ 1100 mm with a small amount increase of electron current of 10%. The obtained beam current fulfills the requirement for JT-60SA.

Journal Articles

Origin of non-uniformity of the source plasmas in JT-60 negative ion source

Yoshida, Masafumi; Hanada, Masaya; Kojima, Atsushi; Inoue, Takashi; Kashiwagi, Mieko; Grisham, L. R.*; Akino, Noboru; Endo, Yasuei; Komata, Masao; Mogaki, Kazuhiko; et al.

Plasma and Fusion Research (Internet), 8(Sp.1), p.2405146_1 - 2405146_4, 2013/11

Distributions of H$$^{0}$$ and H$$^{+}$$ in the source plasmas produced at the end-plugs of JT-60 negative ions source were measured by Langmuir probes and emission spectroscopy in order to experimentally investigate the cause of lower density of the negative ions extracted from end-plugs in the source. Densities of H$$^{0}$$ and H$$^{+}$$ in end-plugs of the plasma grid in the source were compared with those in the center regions. As a result, lower density of the negative ion at the edge was caused by lower beam optics due to lower and higher density of the H$$^{0}$$ and H$$^{+}$$.

JAEA Reports

Operating Document on Management Division Waste Management Section in Tokai Works in the 2003 Fiscal Year

Kobayashi, Kentaro; Akutsu, Shigeru; Sasayama, Yasuo; Nakanishi, Masahiro; Ozone, Takashi; Tomomi, Terunuma,; Mogaki, Isao*

JNC TN8440 2005-007, 138 Pages, 2005/07

JNC-TN8440-2005-007.pdf:7.47MB

This document is announced about the task of Waste Management Section of Waste Management Division in 2003. Mainly, our tasks are fractionating, incinerating and storing low active solid waste and storing high active solid waste. In addition, we are performing required correspondence about management program of low level waste. We had treated and stored waste safely according to our plan. As a result, we have achieved following outcomes. 1. We incinerated the combustible low active solid waste that is generated by the operation of Tokai Reprocessing Plant and the recovery operation of incident at Low Active Liquid Waste Asphalt Solidification Facility. Waste of this recovery operation is stored in the 2nd Low Active Liquid Waste Asphalt Solidification Storage Facility. We incinerated 58 ton of wastes. 2. We stored low active solid waste 854 drums that accommodate 200L. According to the time of Low-Level Waste Treatment Facility completion, we will be able to avoid full of storage. 3. We stored high active solid waste of 148 drums that accommodate 200L. For the time being, there is no problem as regards the administration of storage facility. 4. We carried out the management program of low level solid waste according to plan.

Oral presentation

Technical support for planning and installation of simple ground repository; FY2011 status of support activities for promotion of decontamination in the Fukushima Environmental Safety Center, JAEA

Abe, Hironobu; Ikeda, Koki; Mikake, Shinichiro; Nagasaki, Yasushi; Niizato, Tadafumi; Asazuma, Shinichiro; Aoki, Isao; Ishikawa, Nobuyuki; Ishikawa, Hiroyasu; Ishizaki, Nobuhiro; et al.

no journal, , 

no abstracts in English

Oral presentation

JAEA's technical knowhow for environmental remediation of Fukushima, 1; Technical supports for local governments (Consistency confirmation with Decontamination-related guidelines to national forest temporary storage settings)

Sumiya, Masato; Ikeda, Koki; Sonoda, Takashi; Niizato, Tadafumi; Mikake, Shinichiro; Abe, Hironobu; Inoue, Makoto; Eguchi, Kazutoshi; Kozawa, Masachiyo; Terunuma, Akihiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Completion of decommissioning project of RI using facility

Takai, Toshihide; Shimakawa, Satoshi; Terunuma, Takashi; Aita, Hideki; Midorikawa, Hiroshi

no journal, , 

Decommissioning project of RI using facility was started on 2011 and finished on 2013. The Great East Japan Earthquake was occurred during this period, and a lot of radioactive materials were released to an atmosphere of the wide area because of Fukushima Nuclear Accident. Considering the effect of fallout derived from foregoing accident was required to complete this project.

Oral presentation

Clean-up activity of spent fuel powder (UO$$_{2}$$ powder) in mechanical treatment cell at Tokai Reprocessing Plant

Furuuchi, Yuta; Sato, Shinji; Yatabe, Hitoshi; Yokota, Satoru; Yamada, Takashi; Yahagi, Fumio; Terunuma, Hirotaka; Tokoro, Takeshi; Takahashi, Akihiro; Iijima, Shizuka; et al.

no journal, , 

Clean-up activity of spent fuel powder (UO$$_{2}$$ powder) in mechanical treatment cell was performed for the purpose of the preparation of decommissioning at TRP. For the clean-up activity, we selected an inexpensive vacuum cleaner and made tools, that was improved taking into account of use by means of a crane or a manipulator in the high dose cell, and applied it after a mock-up test. We report our experience and knowledge provided through this clean-up activity.

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