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Journal Articles

Operation and commissioning of IFMIF (International Fusion Materials Irradiation Facility) LIPAc injector

Okumura, Yoshikazu; Gobin, R.*; Knaster, J.*; Heidinger, R.*; Ayala, J.-M.*; Bolzon, B.*; Cara, P.*; Chauvin, N.*; Chel, S.*; Gex, D.*; et al.

Review of Scientific Instruments, 87(2), p.02A739_1 - 02A739_3, 2016/02

 Times Cited Count:7 Percentile:35.23(Instruments & Instrumentation)

IFMIF is an accelerator based neutron facility having two set of linear accelerators each producing 125mA/CW deuterium ion beams (250mA in total) at 40MeV. The LIPAc (Linear IFMIF Prototype Accelerator) being developed in the IFMIF-EVEDA project consists of an injector, a RFQ accelerator, and a part of superconducting Linac, whose target is to demonstrate 125mA/CW deuterium ion beam acceleration up to 9MeV. The injector has been developed in CEA Saclay and already demonstrated 140mA/100keV deuterium beam. The injector was disassembled and delivered to the International Fusion Energy Research Center (IFERC) in Rokkasho, Japan, and the commissioning has started after its reassembly 2014; the first beam production has been achieved in November 2014. Up to now, 100keV/120mA/CW hydrogen ion beam has been produced with a low beam emittance of 0.2 $$pi$$.mm.mrad (rms, normalized).

Journal Articles

Measurement of ion species in high current ECR H$$^+$$/D$$^+$$ ion source for IFMIF (International Fusion Materials Irradiation Facility)

Shinto, Katsuhiro; Sen$'e$e, F.*; Ayala, J.-M.*; Bolzon, B.*; Chauvin, N.*; Gobin, R.*; Ichimiya, Ryo; Ihara, Akira; Ikeda, Yukiharu; Kasugai, Atsushi; et al.

Review of Scientific Instruments, 87(2), p.02A727_1 - 02A727_3, 2016/02

 Times Cited Count:8 Percentile:39.15(Instruments & Instrumentation)

Journal Articles

Present status of the injector for IFMIF Linear Prototype Accelerator (LIPAc)

Shinto, Katsuhiro; Ichikawa, Masahiro; Takahashi, Hiroki; Kondo, Keitaro; Kasugai, Atsushi; Gobin, R.*; Sen$'e$e, F.*; Chauvin, N.*; Ayala, J.-M.*; Marqueta, A.*; et al.

Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.493 - 495, 2015/09

Development of the prototype accelerator (LIPAc) for the engineering validation of the International Fusion Materials Irradiation Facility (IFMIF) which is an accelerator driven neutron source has been progressed at Rokkasho. The LIPAc is a deuteron linear accelerator consisting of an injector, a radio-frequency quadrupole (RFQ) linac and a superconducting linac. The objective of LIPAc is to produce a CW beam with the energy and current of 9 MeV and 125 mA, respectively. The injector was developed at CEA/Saclay and succeeded to produce CW proton and deuteron beams of 100 keV/140 mA by autumn 2012. After the test at CEA/Saclay, the injector was shipped to the International Fusion Energy Research Centre (IFERC) in Rokkasho, Aomori and started to reassemble from the end of 2013. It was successfully produced proton beams in November 2014 at Rokkasho. While the ion source conditioning was done, the beam test was progressed. In this paper, the present status of the LIPAc injector at Rokkasho with some experimental results will be presented.

Journal Articles

Progress of the high current Prototype Accelerator for IFMIF/EVEDA

Okumura, Yoshikazu; Ayala, J.-M.*; Bolzon, B.*; Cara, P.*; Chauvin, N.*; Chel, S.*; Gex, D.*; Gobin, R.*; Harrault, F.*; Heidinger, R.*; et al.

Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.203 - 205, 2015/09

Under the framework of Broader Approach (BA) agreement between Japan and Euratom, IFMIF/EVEDA project was launched in 2007 to validate the key technologies to realize IFMIF. The most crucial technology to realize IFMIF is two set of linear accelerator each producing 125mA/CW deuterium ion beams up to 40MeV. The prototype accelerator, whose target is 125mA/CW deuterium ion beam acceleration up to 9MeV, is being developed in International Fusion Research Energy Center (IFERC) in Rokkasho, Japan. The injector developed in CEA Saclay was delivered in Rokkasho in 2014, and is under commissioning. Up to now, 100keV/120mA/CW hydrogen ion beams and 100keV/90mA/CW duty deuterium ion beams are successfully produced with a low beam emittance of 0.21 $$pi$$.mm.mrad (rms, normalized). Delivery of RFQ components will start in 2015, followed by the installation of RF power supplies in 2015.

Journal Articles

Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi Nuclear Power Station

Ikeuchi, Hirotomo; Kondo, Yoshikazu*; Noguchi, Yoshihiro*; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), p.1349 - 1356, 2013/09

Journal Articles

Analysis of sludge in the dissolver and survey of the behavior of zirconium molybdate

Kondo, Yoshikazu; Uchida, Naoki; Terunuma, Hirotaka; Tanaka, Kosuke; Oyama, Koichi; Katsurai, Kiyomichi; Washiya, Tadahiro

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.277 - 280, 2009/09

The composition of sludge in the dissolver after dissolution of PWR and ATR fuels at the Tokai Reprocessing Plant (TRP) was analyzed. As a result the presence of zirconium molybdate was confirmed by the analysis of X-ray diffraction (XRD). To clarify the formation behavior of the precipitates of zirconium molybdate, investigated the dependence of HNO$$_{3}$$ concentration on the precipitation with Mo and Zr solution. To evaluate the adhesion on the metal surface (stainless steel and Ti metal), the deposition amounts of the precipitates of zirconium molybdate on the metal were also examined. In addition, it reports on the comparative result of executing a chemical dissolution of the precipitates by using the solutions of NaOH, C$$_{2}$$H$$_{2}$$O$$_{4}$$-HNO$$_{3}$$ and H$$_{2}$$O$$_{2}$$-HNO$$_{3}$$.

Oral presentation

Status of IFMIF target system development

Nakamura, Hiroo; Ida, Mizuho; Miyashita, Makoto; Yoshida, Eiichi; Ara, Kuniaki; Nishitani, Takeo; Okumura, Yoshikazu; Horiike, Hiroshi*; Kondo, Hiroo*; Terai, Takayuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 3; Evaluation of pressure increase by dissolution reaction in dissolver

Oyama, Koichi; Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Nagata, Masanobu*; Horiuchi, Nobutake*; Chikazawa, Takahiro*; Kikuchi, Toshiaki*

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel

Oyama, Koichi; Katsurai, Kiyomichi; Nomura, Kazunori; Takeuchi, Masayuki; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 5; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Takizawa, Takeyuki*; Yamashita, Kazuhiko*

no journal, , 

This report presents a knowledge getting from endurance test of the bearing for rotary dram type continuous dissolver which is under development as one of the Fast Reactor Cycle technology Development Project in JAEA. Non lubricant type bearing is preferable to endure heavy radiation environment but abrasion of the bearing is concerned due to heavy weigh and low swing motion. Small scale of the endurance test of the bearing using 4 types of candidates including all-ceramics and hybrid ceramics roll bearing, carbon slide bearing and air bearing was implemented. This report demonstrates the test results of the screening and a way of the improvement for select one.

Oral presentation

Development of sludge management technology on FBR fuel reprocessing, 1; Removal experiment of zirconium molybdate

Kondo, Yoshikazu; Katsurai, Kiyomichi; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

To investigate the chemical washing method of zirconium molybdate, the washing character using NaOH, C$$_{2}$$H$$_{2}$$O$$_{4}$$ and H$$_{2}$$O$$_{2}$$ were examined using the simulated solution of fuel dissolution process. Also we evaluated the deposition amounts of zirconium molybdate on the metal surface in the simulated solution.

Oral presentation

Development of highly effective dissolution technology for FBR MOX fuels

Ikeuchi, Hirotomo; Katsurai, Kiyomichi; Kondo, Yoshikazu; Sano, Yuichi; Washiya, Tadahiro; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Development of sludge management technology for FBR MOX fuel, 2; Dependence of sludge amounts on the burn-up using simulated spent fuel

Takeuchi, Masayuki; Kondo, Yoshikazu; Washiya, Tadahiro; Nakamura, Kazuhito*

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 6; Estimation of crevice corrosion rate of dissolver structural materials

Ikeuchi, Hirotomo; Katsurai, Kiyomichi; Kondo, Yoshikazu; Sano, Yuichi; Washiya, Tadahiro; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel

Hoshino, Takanori; Ikeuchi, Hirotomo; Katsurai, Kiyomichi; Kondo, Yoshikazu*; Shibata, Atsuhiro; Sano, Yuichi; Watanabe, Masayuki; Suganuma, Takashi

no journal, , 

no abstracts in English

Oral presentation

Characterization of precipitates formed in simulated high-level liquid wastes

Murao, Ayako*; Mimura, Hitoshi*; Kirishima, Akira*; Kondo, Yoshikazu*; Nomura, Kazunori; Washiya, Tadahiro

no journal, , 

Oral presentation

Thermodynamic calculation on chemical forms of in-vessel debris of Fukushima-Daiichi NPP

Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu*; Noguchi, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Estimation of chemical forms of in-vessel fuel-debris by combination of melt-progression analysis and thermodynamic equilibration

Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu*; Noguchi, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Chemical form estimation of in-vessel fuel debris by thermodynamic calculation with melt progression analysis

Ikeuchi, Hirotomo; Noguchi, Yoshihiro*; Kondo, Yoshikazu*; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro

no journal, , 

Oral presentation

Commissioning of the injector for the IFMIF/EVEDA Prototype Accelerator (LIPAc)

Shinto, Katsuhiro; Kasugai, Atsushi; Kondo, Keitaro; Takahashi, Hiroki; Ichimiya, Ryo; Gobin, R.*; Sen$'e$e, F.*; Bolzon, B.*; Chauvin, N.*; Valette, M.*; et al.

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)