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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:5 Percentile:50.71(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

Overview on recent progress toward small specimen test technique

Wakai, Eiichi; Kikuchi, Takayuki; Kim, B.*; Kimura, Akihiko*; Nogami, Shuhei*; Hasegawa, Akira*; Nishimura, Arata*; Soldaini, M.*; Yamamoto, Michiyoshi*; Knaster, J.*

Fusion Engineering and Design, 98-99, p.2089 - 2093, 2015/10

 Times Cited Count:8 Percentile:23.02(Nuclear Science & Technology)

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

The Accomplishment of the engineering design activities of IFMIF/EVEDA; The European-Japanese project towards a Li(d,xn) fusion relevant neutron source

Knaster, J.*; Ibarra, A.*; Ida, Mizuho*; Kondo, Keitaro; Kikuchi, Takayuki; Ohira, Shigeru; Sugimoto, Masayoshi; Wakai, Eiichi; Watanabe, Kazuhito; 58 of others*

Nuclear Fusion, 55(8), p.086003_1 - 086003_30, 2015/08

 Times Cited Count:46 Percentile:1.4(Physics, Fluids & Plasmas)

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, has accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF plant, which is here described. Many improvements of the design from former phases are implemented, particularly a reduction of beam losses and operational costs thanks to the superconducting accelerator concept. In the Test Cell design, the separation of the irradiation modules from the shielding block gaining irradiation flexibility and enhancement of the remote handling equipment reliability and cost reduction. The released IFMIF Intermediate Engineering Design Report, which could be complemented if required concurrently with the outcome of the on-going EVA carried out since the entry into force of IFMIF/EVEDA in June 2007, will allow the decision making on its construction and/or serve as the basis for the definition of the next step, aligned with the evolving needs of our fusion community.

Journal Articles

Status quo of the injector for the IFMIF/EVEDA prototype accelerator

Shinto, Katsuhiro; Ichikawa, Masahiro; Takahashi, Yasuyuki*; Kubo, Takashi*; Tsutsumi, Kazuyoshi; Kikuchi, Takayuki; Kasugai, Atsushi; Sugimoto, Masayoshi; Gobin, R.*; Girardot, P.*; et al.

Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1009 - 1012, 2014/10

The prototype accelerator is being developed as an engineering validation for the International Fusion Materials Irradiation Facility (IFMIF) equipped with an accelerator-driven-type neutron source for developing fusion reactor materials. This prototype accelerator is a deuteron linear accelerator consisting of an injector, an RFQ, a superconducting linac and their auxiliaries. It aims to produce a CW D$$^+$$ beam with the energy and current of 9 MeV/125 mA. The injector test was completed at CEA/Saclay in 2012 for producing a CW H$$^+$$ beam and a CW D$$^+$$ beam with the energy and current of 100 keV/140 mA. After the beam test at CEA/Saclay, the injector was transported to the International Fusion Energy Research Centre (IFERC) located in Rokkasho, Aomori, Japan. In the end of 2013, installation of the injector was started at IFERC for the injector beam test beginning from summer 2014 in order to obtain better beam qualities to be satisfied with the injection and acceleration of the following accelerators. In this paper, some results of the injector beam test performed at CEA/Saclay and the status quo of the installation of the injector at IFERC are presented.

Journal Articles

Generation of radioisotopes with accelerator neutrons by deuterons

Nagai, Yasuki; Hashimoto, Kazuyuki; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji; Sonoda, Nozomi; Kawabata, Masako; Harada, Hideo; Kin, Tadahiro*; Tsukada, Kazuaki; et al.

Journal of the Physical Society of Japan, 82(6), p.064201_1 - 064201_7, 2013/06

 Times Cited Count:28 Percentile:15.17(Physics, Multidisciplinary)

Journal Articles

Corrosion behavior of Fe, Cr, Ni and their alloys in sodium molybdate melts

Nagai, Takayuki; Kikuchi, Kotaro*; Kano, Yoshiharu*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 12(1), p.76 - 88, 2013/03

To understand the corrosion behavior of stainless steel and Ni-Cr alloys in sodium molybdate melts, the immersed corrosion tests of Fe, Cr, Ni, SUS316, 55Ni-45Cr, and Inconel 690 specimens were carried out in Na$$_{2}$$MoO$$_{4}$$ and Na$$_{2}$$Mo$$_{2}$$O$$_{7}$$ melts at 750 $$^{circ}$$C. The results of the immersed test, it was found that the corrosion rate decreased with an increase of chromium content in chemical composition of specimens. It was observed that Cr$$_{2}$$O$$_{3}$$ formed on the surface of Cr, 55Ni-45Cr, and Inconel 690 specimens by immersed in Na$$_{2}$$Mo$$_{2}$$O$$_{7}$$ melt, which corrosion rates were low in the melt, and we presumed that this Cr$$_{2}$$O$$_{3}$$ on the surface controlled the corrosion behavior of their material in the melt.

Journal Articles

Development of small specimen test techniques for the IFMIF test cell

Wakai, Eiichi; Kim, B. J.; Nozawa, Takashi; Kikuchi, Takayuki; Hirano, Michiko*; Kimura, Akihiko*; Kasada, Ryuta*; Yokomine, Takehiko*; Yoshida, Takahide*; Nogami, Shuhei*; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 6 Pages, 2013/03

Journal Articles

Analysis of test matrix and design status of test modules of IFMIF

Wakai, Eiichi; Kikuchi, Takayuki; Yokomine, Takehiko*; Yamamoto, Michiyoshi; Soldaini, M.*; Polato, A.*

Fusion Science and Technology, 62(1), p.246 - 251, 2012/07

 Times Cited Count:6 Percentile:45.33(Nuclear Science & Technology)

Journal Articles

Basic design guideline for the preliminary engineering design of PIE facilities in IFMIF/EVEDA

Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*

Fusion Engineering and Design, 86(12), p.2904 - 2907, 2011/12

 Times Cited Count:3 Percentile:67.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Status of Japanese design and validation activities of test facilities in IFMIF/EVEDA

Wakai, Eiichi; Kikuchi, Takayuki; Kogawara, Takafumi; Kimura, Haruyuki; Yokomine, Takehiko*; Kimura, Akihiko*; Nogami, Shuhei*; Kurishita, Hiroaki*; Saito, Masahiro*; Nishimura, Arata*; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03

Japanese activities of test facilities in IFMIF-EVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) project have three subjects of engineering design of post irradiation examination (PIE) facilities, small specimen test technique (SSTT), and engineering design of high flux test module (HFTM), and this paper is summarized about present status. Functional analysis and design of 2-D and 3-D models of PIE facility were performed. In HFTM, as materials of heater, W-3Re alloy and/or SiC/SiC composite were selected in the points of high temperature materials, fabrication technology and some suitable properties such as resistance of thermal shock, high temperature re-crystallization, ductility, resistance of irradiation degradation, and low-activation. In SSTT, a test machine of fracture toughness was designed and developed for small specimens with 10 mm square, and it had high accuracy controllability for stress and displacement.

Journal Articles

Design status of post irradiation examination facilities in IFMIF/EVEDA

Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki

Journal of Plasma and Fusion Research SERIES, Vol.9, p.242 - 247, 2010/08

Recent progress of preliminary engineering design of post irradiation examination (PIE) facilities of IFMIF-EVEDA (International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities) was summarized. The PIE Facilities have mainly hot cells and preparation rooms for some examinations and tests of the materials irradiated in the high-, medium- and low-flux test modules, back plate of Li target, and the others of IFMIF. In this study a basic functional analysis was performed, and handling process of specimen reloading and radiation-shielding wall in hot cells was also evaluated. Based on the results, a layout of PIE facilities was designed.

JAEA Reports

Development of mechanical seal structure for reuse of re-instrumentation device used in fuel irradiation test

Inoue, Shuichi; Yamaura, Takayuki; Saito, Takashi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; Sozawa, Shizuo; Tsuchiya, Kunihiko

JAEA-Technology 2009-076, 33 Pages, 2010/03

JAEA-Technology-2009-076.pdf:18.29MB

In Japan Material Testing Reactor (JMTR), a lot of experiments of fuel irradiation with the power ramping tests have been performed by using the shroud irradiation facility and the Boiling Water Capsule (BOCA). The fuel samples used in these tests were welded to re-instrumentation devices such as thermocouples and FP gas pressures. In this development, the mechanical connection method as "mechanical seal structure", that enables the re-use of re-instrumentation devices, was adopted in order to improve the utilization efficiency of the device. The test samples with mechanical seal structure were fabricated and the confirmatory tests such as He leakage test, thermal cycle test, autoclave test, etc. were carried out. The test samples with the mechanical seal structure showed an excellent result in various confirmatory tests, and the prospect are bright for the re-use of re-instrumentation devices with the mechanical seal structure.

Journal Articles

Progress of the IFMIF/EVEDA prototype accelerator in the Broader Approach activities for fusion energy in FY2008

Shinto, Katsuhiro; Vermare, C.*; Asahara, Hiroo; Sugimoto, Masayoshi; Garin, P.*; Maebara, Sunao; Takahashi, Hiroki; Sakaki, Hironao; Kojima, Toshiyuki; Ohira, Shigeru; et al.

Proceedings of 6th Annual Meeting of Particle Accelerator Society of Japan (CD-ROM), p.668 - 670, 2010/03

Progress of the IFMIF/EVEDA prototype accelerator in fiscal year of 2008 is described. All the sub-systems of the prototype accelerator have started to design, settled the plan of the manufacturing and component tests and fixed the design parameters. As a result of the analysis of planning for the engineering validation of the IFMIF accelerator system, the project duration to be prolonged to the end of 2014 including some months for contingency was approved by the BA Steering Committee. In this article, the design status of each accelerator component, the interface between the accelerator components and the IFMIF/EVEDA Accelerator Building settled in International Fusion Energy Research Centre (IFERC) in Rokkasho and the proposed accelerator commissioning plan for the engineering validation will be presented.

Journal Articles

Corrosion behavior of SUS316 clad in alkalis molybdate melt

Nagai, Takayuki; Kikuchi, Kotaro*; Kano, Yoshiharu*; Fukushima, Mineo

Nippon Genshiryoku Gakkai Wabun Rombunshi, 7(4), p.370 - 379, 2008/12

Study of a new pyrochemical processing using alkaline molybdate melt has been carrying out as a candidate reprocessing process for spent oxide fuels. In our previous study, we had confirmed that melting of UO$$_{2}$$ pellet into a molten Na$$_{2}$$MoO$$_{4}$$-MoO$$_{3}$$ and electrolytic recovering of UO$$_{2}$$ from the melt included uranyl ions. In this report, the corrosion behavior of the SUS316 cladding tube in molten Na$$_{2}$$MoO$$_{4}$$-MoO$$_{3}$$ was evaluated, and we confirmed the dissolution of SUS316 elements into the melt when the amount of additional MoO$$_{3}$$ was excess. And, it is necessary to understand an appropriate amount of additional MoO$$_{3}$$ since the result of this study.

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

JAEA Reports

Basis data for surveillance test on core support graphite structures for the High Temperature Engineering Test Reactor (HTTR)

Sumita, Junya; Shibata, Taiju; Kikuchi, Takayuki; Ishihara, Masahiro; Iyoku, Tatsuo; Sawa, Kazuhiro; Fujimoto, Nozomu

JAEA-Data/Code 2007-001, 57 Pages, 2007/02

JAEA-Data-Code-2007-001.pdf:3.0MB

Visual inspection by a TV camera and material properties measurement by surveillance test on core support graphite structures are planned for the High Temperature Engineering Test Reactor (HTTR) to confirm their structural integrity and characteristics. The surveillance test is aimed to investigate the change of material and mechanical properties by aging effects such as fast neutron irradiation and oxidation. The obtained data will be used not only for evaluating the structural integrity of the core support graphite structure of the HTTR but also for design data to advanced Very High Temperature Reactor (VHTR) discussed at generation IV international forum. This report describes the material properties and installed position of surveillance specimens in the HTTR in order to carry out the surveillance test.

Journal Articles

R&D for HTGRs core components

Hanawa, Satoshi; Shibata, Taiju; Sumita, Junya; Kikuchi, Takayuki; Sawa, Kazuhiro; Ishihara, Masahiro; Iyoku, Tatsuo

Koon Gakkai-Shi, 32(1), p.36 - 42, 2006/01

no abstracts in English

JAEA Reports

Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (III) Final Report

Ikusawa,Yoshihisa; Kikuchi,Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Isozaki,Takao*; Nagayama, Masahiro*

JNC-TN8410 2005-012, 113 Pages, 2005/08

JNC-TN8410-2005-012.pdf:15.2MB

The E09 fuel assembly was irradiated in the FUGEN from February 1990 to January 1997. The fuel assembly was the highest burn-up assembly in FUGEN and the pellet peak burn-up reached about 48 GWd/t. The E09 fuel assembly was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001. Post Irradiation Examinations (PIE) were started in July 2001, and all PIE items were completed by March 2005. The irradiation behavior of E09 MOX fuel was evaluated from the result of PIE. The major results are as follows; The integrity of E09 fuel assembly and fuel rods was confirmed. The corrosion behavior of ATR MOX fuel cladding was similar to that of LWR-UO2 fuel cladding. The central void was observed in outer ring samples irradiated with the maximum linear power over 45kW/m. A porous fine structure, similar to the rim structure seen in LWR-UO$$_{2}$$ pellet, was observed in the circumferential region of MOX pellet and around the plutonium-rich spots. The MOX fuel properties irradiated up to ~48 GWd/t, which are pellet swelling, thermal conductivity, pellet melting temperature and diffusivity of fission gas, were similar to LWR-UO$$_{2}$$ fuel properties. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.

JAEA Reports

Post Irradiation Examination for The FUGEN High Burn-up MOX Fuel Assembly (II) Destructive Examination

Ikusawa,Yoshihisa; Keiichi, Kikuchi,; Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*

JNC-TN8410 2004-008, 106 Pages, 2004/10

JNC-TN8410-2004-008.pdf:25.96MB

The "E09" was irradiated in the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t at the end of irradiation. In order to be irradiated up to high burn-up, this fuel assembly had the design improved by applying the fissile content with axial distribution, four UO$$_{2}$$- Gd$$_{2}$$O$$_{3}$$fuel rods located with MOX fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation.After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001.Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination, Ceramography, Metallography and alpha-autoradiography) were completed in March 2003. The destructive examinations will be completed by December 2004.In this report, the data obtained from destructive examinations completed in March 2003 were summarized, and the evaluation results of irradiation performance of MOX fuel and cladding were discussed. Consequently, the MOX fuel rod integrity during irradiation was confirmed from the result of the destructive PIE. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.

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