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

https://doi.org/10.1063/1.4936248

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 .mm.mrad (rms, normalized).

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

https://doi.org/10.13182/FST13-770

Overview of materials research and IFMIF-EVEDA under the Broader Approach framework

Nishitani, Takeo; Tanigawa, Hiroyasu; Yamanishi, Toshihiko; Clement Lorenzo, S.*; Baluc, N.*; Hayashi, Kimio; Nakajima, Noriyoshi*; Kimura, Haruyuki; Sugimoto, Masayoshi; Heidinger, R.*; et al.

Fusion Science and Technology, 62(1), p.210 - 218, 2012/07

https://doi.org/10.13182/FST12-A14137

Recent progress in the material related researches and the IFMIF/EVEDA project, which are carried out under the Broader Approach (BA) framework, is reported. In the International Fusion Energy Research Center (IFERC) project of BA, the R&D building was completed March 2010 at the Rokkasho BA site. R&Ds on reduced activation ferritic/ martensitic (RAFM) steels as structural material, SiC/SiC composites as a flow channel insert material and/or alternative structural material, advanced tritium breeders and neutron multipliers, and tritium technology relevant to the DEMO operational condition are progressed in Japan and EU. In the IFMIF/EVEDA project, the fabrication of the injector for the IFMIF prototype accelerator was completed at the CEA Saclay, and the first proton beam was obtained in May, 2011. The IFMIF lithium target test loop was completed in March 2011, and a lithium flow of 5 m/s was obtained.

Commissioning of the IFMIF/EVEDA accelerator prototype; Objectives & plans

Vermare, C.*; Garin, P.*; Shidara, H.*; Beauvais, P. Y.*; Mosnier, A.*; Ibarra, A.*; Heidinger, R.*; Facco, A.*; Pisent, A.*; Maebara, Sunao; et al.

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.777 - 779, 2010/05

http://accelconf.web.cern.ch/AccelConf/IPAC10/papers/mopd042.pdf

Design of electron cyclotron heating and current drive system of ITER

Kobayashi, Noriyuki; Bigelow, T.*; Bonicelli, T.*; Cirant, S.*; Denisov, G.*; Heidinger, R.*; Henderson, M.*; Hogge, J.-P.*; Piosczyk, B.*; Ramponi, G.*; et al.

AIP Conference Proceedings 933, p.413 - 416, 2007/10

https://doi.org/10.1063/1.2800520

Since the EDA 2001, Design of Electron Cyclotron Heating and Current Drive (ECH&CD) System have been modified due to progress of physics understanding and change of interface. Nominal RF power 20 MW is injected by four upper launchers or one equatorial launcher. RF beams are steered by a front steering mirror. DCHV power supply will be composed of IGBT pulse step modulators because of high frequency modulation and design flexibility to three different types of 170 GHz gyrotrons from three parties. The RF power is transmitted by 63.5 mm dia corrugated waveguide and switched by a waveguide switch between the upper launcher and the equatorial launcher. A start-up system for initial discharge is composed of three 127.5 GHz gyrotrons and dedicated DCHV power supply. Three of transmission lines are shared between 170 GHz and 127.5 GHz gyrotrons to inject start-up RF beam through the equatorial launcher. R&Ds for high power long pulse have been on-going to obtain a reliable ITER ECH&CD system.

Development of EC launcher and diamond window for ITER

Takahashi, Koji; Sakamoto, Keishi; Imai, Tsuyoshi; Kasugai, Atsushi; Heidinger, R.*; Thumm, M.*; Moeller, C. P.*

Proceedings of IAEA TM on ECRH Physics and Technology for ITER (CD-ROM), 7 Pages, 2003/00

A front steering (FS) launcher and a remote steering (RS) one have been studied for ITER. In the analysis of a mirror(Cu alloy) for FS launcher, max. temperature of 333C and max. induced stress of 136MPa, less than allowable stress(200MPa), were obtained at the mirror surface under 1MW/1line in CW operation. The efficient transmission (95%) at -1212 and 170GHz was performed for both polarizations in the experiments of a square corrugated waveguide for the RS launcher. RF and pressure tests of the diamond window irradiated by neutron were carried under JA/EU(FZK) collaboration. Neutron fluence of the window was 10n/m, whereas the estimated annual fluence at the window position is 1010n/m. Transmission of 0.48MW-30sec and 0.2MW-132sec were performed. It was successfully demonstrated that the irradiated window withstood 0.4MPa, which was twice higher than the ITER requirement. Diamond windows are applicable for ITER.

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.

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.