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Journal Articles

Experimental study on cavitation of a liquid lithium jet for International Fusion Materials Irradiation Facility

Kondo, Hiroo; Kanemura, Takuji*; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi; Knaster, J.*

Journal of Nuclear Engineering and Radiation Science, 3(4), p.041005_1 - 041005_11, 2017/10

A liquid-Li free-surface stream flowing at 15 m/s under a high vacuum of 10$$^{-3}$$ Pa is to serve as a beam target (Li target) for the planned International Fusion Materials Irradiation Facility (IFMIF) or other intense fusion neutron sources. This study focuses on cavitation-like acoustic noise which was detected in a conduit downstream from the Li target. This noise was measured by using acoustic-emission (AE) sensors that were installed at several locations of the conduit via acoustic wave guides. As a result, we found that cavitation occurred only in a narrow area where the Li target impinged on the downstream conduit.

Journal Articles

Validation of liquid lithium target stability for an intense neutron source

Kondo, Hiroo; Kanemura, Takuji*; Furukawa, Tomohiro; Hirakawa, Yasushi; Wakai, Eiichi; Knaster, J.*

Nuclear Fusion, 57(6), p.066008_1 - 066008_10, 2017/07

 Times Cited Count:14 Percentile:66.43(Physics, Fluids & Plasmas)

A liquid-Li free-surface stream flowing at 15 m/s under a high vacuum of 10$$^{-3}$$ Pa is to serve as a beam target (Li target) for the planned International Fusion Materials Irradiation Facility (IFMIF) or other intense fusion neutron sources. We determined that the stability of the Li target remained unchanged despite using it for an extended period of 1,561 h. This finding is regarded as a significant step toward the realization of the IFMIF and the potential use of relevant neutron sources such as A-FNS and DONES.

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:35.45(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:14 Percentile:77.78(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:58 Percentile:95.37(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 of development of Lithium Target Facility in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Hoashi, Eiji*; Fukada, Satoshi*; Suzuki, Akihiro*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.

Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11

In the IFMIF/EVEDA (International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity), the validation tests of the EVEDA lithium test loop with the world's highest flow rate of 3000 L/min was succeeded in generating a 100 mm-wide and 25 mm-thick free-surface lithium flow steadily under the IFMIF operation condition of a high-speed of 15 m/s at 250$$^{circ}$$C in a vacuum of 10 $$^{-3}$$ Pa. Some excellent results of the recent engineering validations including lithium purification, lithium safety, and remote handling technique were obtained, and the engineering design of lithium facility was also evaluated. These results will advance greatly the development of an accelerator-based neutron source to simulate the fusion reactor materials irradiation environment as an important key technology for the development of fusion reactor materials.

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.

Fusion Science and Technology, 66(1), p.46 - 56, 2014/07

 Times Cited Count:4 Percentile:31.13(Nuclear Science & Technology)

Journal Articles

IFMIF; Overview of the validation activities

Knaster, J.*; Arbeiter, F.*; Cara, P.*; Favuzza, P.*; Furukawa, Tomohiro; Groeschel, F.*; Heidinger, R.*; Ibarra, A.*; Matsumoto, Hiroshi*; Mosnier, A.*; et al.

Nuclear Fusion, 53(11), p.116001_1 - 116001_18, 2013/11

AA2013-0294.pdf:2.55MB

 Times Cited Count:62 Percentile:94.3(Physics, Fluids & Plasmas)

The IFMIF/EVEDA project under the Broader Approach Agreement between Japan and EU aims at allowing a rapid construction phase of IFMIF in due time. The three main facilities, (1) the Accelerator Facility, (2) the Target Facility and (3) the Test Facility, are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho. The world largest liquid Li test loop is running in Oarai with an ambitious experimental programme for the years ahead. A full scale high flux test module that will house $$sim$$ 1000 small specimens developed jointly in Europe and Japan has been constructed in Germany together with its He gas loop. A full scale medium flux test module to carry out on-line creep measurement has been constructed in Switzerland.

Journal Articles

Status report on the toroidal field coils for the ITER project

Savary, F.*; Bonito Oliva, A.*; Gallix, R.*; Knaster, J.*; Koizumi, Norikiyo; Mitchell, N.*; Nakajima, Hideo; Okuno, Kiyoshi; Sborchia, C.*

IEEE Transactions on Applied Superconductivity, 20(3), p.381 - 384, 2010/06

 Times Cited Count:19 Percentile:67.38(Engineering, Electrical & Electronic)

no abstracts in English

Oral presentation

Fusion technology activities through the Broader Approach IFMIF-EVEDA project

Matsumoto, Hiroshi; Knaster, J.*; Heidinger, R.*; Sugimoto, Masayoshi; Ibarra, A.*; Mosnier, A.*; Heinzel, V.*; Massaut, V.*; Micciche, G.*; M$"o$slang, A.*

no journal, , 

The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design and Engineering Validation Activities (EVEDA) started in 2007 under the framework of the Broader Approach (BA) Agreement between EU and Japan with the objective of developing a complete engineering design of the IFMIF together with accompanying sub projects to validate the major elements of the technologies essential for the IFMIF Plant. The validation sub projects include design and construction of the prototype deuteron beam accelerator, Lithium Loop Test Facility, and irradiation test of samples in Rigs for High Flux Test Modules. The recent achievements from these activities will be presented.

Oral presentation

Result of ITER TF coil sub and full scale trials performed in Japan

Matsui, Kunihiro; Koizumi, Norikiyo; Hemmi, Tsutomu; Takano, Katsutoshi; Kajitani, Hideki; Iguchi, Masahide; Chida, Yutaka; Nakajima, Hideo; Knaster, J.*; Foussat, A.*

no journal, , 

JAEA performed sub- and full-scale trials to development for the Toridal Field (TF) coil manufacture prior to series production of the TF coils. In the sub-scale trials, the conductor winding, insulation/impregnation and heat treatment trials were performed to resolve some technical issues and to demonstrate the fabrication procedures. The followings are major achievements. (1) High accuracy of 0.011% in the conductor winding, (2) the evaluation of 0.073% conductor elongation due to heat treatment and (3) the successful impregnation using CE resin. In the full scale trials, a full scale radial plate (RP) was fabricated, and the flatness of fabricated RP within 2 mm were achieved.

Oral presentation

IFMIF/EVEDA; Progress of validation and design activities under the Broader Approach framework

Sugimoto, Masayoshi; Knaster, J.*; Arbeiter, F.*; Cara, P.*; Favuzza, P.*; Furukawa, Tomohiro; Gioacchino, M.*; Groeschel, F.*; Heidinger, R.*; Ibarra, A.*; et al.

no journal, , 

Under the framework of the Broader Approach agreement between Japan and EURATOM the concept of the International Fusion Materials Irradiation Facility (IFMIF) to provide the intense neutron irradiation test facility for developing the fusion reactor materials has been evolved since 2007, through the activities to prepare the engineering design documents for IFMIF with the associated R&D of prototypical components, named as IFMIF Engineering Validation and Engineering Design Activities (EVEDA) project. Recently the Intermediate IFMIF Engineering Design Report for IFMIF (IIEDR) was delivered in July 2013, which is supported by the major outcomes of the validation activities of the prototypical components: Linear IFMIF Prototype Accelerator, EVEDA Lithium Test Loop, High Flux Test Module capsule, etc. In this article, the progresses of the IIEDR and validation tests and also the outcomes to be achieved till mid 2017, the completion time of IFMIF/EVEDA, will be comprehensively overviewed.

Oral presentation

Status of lithium target facility development in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakaniwa, Koichi; Ito, Yuzuru; Tanaka, Hiroshi; Tsuji, Yoshiyuki*; Ito, Takahiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

LIPAc, the 125 mA / 9 MeV / CW deuteron IFMIF's prototype accelerator; What lessons have we learnt from LEDA ?

Scantamburlo, F.*; Knaster, J.*; Okumura, Yoshikazu; Kasugai, Atsushi; Shidara, Hiroyuki*; Chauvin, N.*; Gobin, R.*; Nghiem, P. A. P.*

no journal, , 

The Engineering Validation and Engineering Design Activities (EVEDA) phase of IFMIF aims at running a 9 MeV / 125 mA / CW deuteron accelerator to demonstrate the feasibility of IFMIF's 40 MeV / 125 mA / CW accelerator with components mainly designed and constructed in European labs. LEDA was operated successfully in 1999-2001 as a 6.7 MeV / 100 mA / CW proton accelerator with high availability. The present paper assesses the experience gained in LEDA and explains how LIPAc, the IFMIF prototype accelerator, is inheriting its role of breaking through technological boundaries.

Oral presentation

FPGA utilization of the accelerator interlock system through MPS development in LIPAc

Nishiyama, Koichi; Takahashi, Hiroki; Sakaki, Hironao; Narita, Takahiro; Kojima, Toshiyuki*; Knaster, J.*; Marqueta, A.*

no journal, , 

The development of IFMIF(International Fusion Material Irradiation Facility) to generate a 14 MeV source of neutrons with the spectrum of DT fusion reactions is indispensable to qualify suitable materials for the First Wall of the nuclear vessel in fusion power plants. As part of IFMIF validation activities, LIPAc (Linear IFMIF Prototype Accelerator) facility, currently under installation at Rokkasho (Japan), will accelerate a 125 mA CW and 9 MeV deuteron beam with a total beam power of 1.125 MW. The Machine Protection System (MPS) of LIPAc provides an essential interlock function of stopping the beam in case of anomalous beam loss or other hazardous situations. High speed processing is necessary to achieve properly the MPS main goal. This high speed processing of the signals, distributed alongside the accelerator facility, is based on FPGA (Field Programmable Gate Array) technology. This paper describes the basis of FPGA use in the accelerator interlock system through the development of LIPAc.

Oral presentation

Evaluation of Lithium Target Facility of IFMIF in IFMIF/EVEDA Project

Wakai, Eiichi; Kanemura, Takuji; Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Micciche, G.*; Heidinger, R.*; Knaster, J.*; Sugimoto, Masayoshi

no journal, , 

Oral presentation

Vision of the neutron source for the post BA activities

Ohira, Shigeru; Ochiai, Kentaro; Sugimoto, Masayoshi; Kasugai, Atsushi; Okumura, Yoshikazu; Ushigusa, Kenkichi; Ibarra, A.*; Heidinger, R.*; Knaster, J.*

no journal, , 

The IFMIF/EVEDA activity has successfully demonstrated a stable lithium flow in the EVEDA Lithium Test Loop and produced preliminary scientific results for the Injector, one of the most challenging parts of the Linear IFMIF Prototype Accelerator (LIPAc). Discussions by the BASC are taking place on the possibility of an extension to fully test the reliability of the LIPAc over a sufficiently long time. Recently there have been assessments in the EU and JA which have concluded that there is a need to have access around 2025 to a facility producing a fusion-like neutron spectrum with a minimum flux about half that of IFMIF- this has been given the name DONES in EU and A-FNS in JA. In this presentation, current status and achievements of the IFMIF/EVEDA was presented as well as the Ideas of the neutron source for the post-BA activities from EU and Japan.

Oral presentation

R&D of lithium target and test facilities for the fusion neutron source

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Kikuchi, Takayuki; Ito, Yuzuru*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Cryoplant system for IFMIF/EVEDA prototype accelerator

Kasugai, Atsushi; Bazin, N.*; Cara, P.*; Chel, S.*; Gex, D.*; Heidinger, R.*; Yoshida, Kiyoshi; Ihara, Akira; Knaster, J.*; Kondo, Keitaro; et al.

no journal, , 

The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at sufficient intensity and irradiation volume for DEMO reactor materials qualification. The IFMIF/EVEDA project, which is part of the Broader Approach (BA) agreement between Japan and EU, has the mission to work on the engineering design of IFMIF and to validate the main technological challenges. The prototype accelerator being developed in the IFMIF-EVEDA project consists of an injector, a RFQ accelerator, and a part of superconducting Linac. The design of the cryoplant for SRF-linac has been already completed and it will be started to install to the facility from coming September after the licensing. This article describes the cryoplant for the IFMIF/EVEDA prototype accelerator facility.

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