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

http://www.pasj.jp/web_publish/pasj2014/proceedings/PDF/SUP0/SUP025.pdf

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.

Research facilities for International Fusion Energy Research Centre of Broader Approach Activities at Rokkasho

Ohira, Shigeru; Utsumi, Shigeo*; Kubo, Takashi; Yonemoto, Kazuhiro; Kasuya, Kenichi; Ejiri, Shintaro; Kimura, Haruyuki; Okumura, Yoshikazu

Journal of Plasma and Fusion Research SERIES, Vol.9, p.665 - 669, 2010/08

http://www.jspf.or.jp/JPFRS/PDF/Vol9/jpfrs2010_09-665.pdf

Under the Agreement Between the Government of Japan and the EURATOM for the Joint Implementation of the Broader Approach Activities (BA Activities) in the Field of Fusion Energy Research, JAEA develop a new site at Rokkasho-mura in Aomori prefecture of Japan as the Japanese Implementing Agency. In this new site, two of the three projects of the BA Activities are to be implemented, namely, International Fusion Energy Research Center (IFERC) Project and International Fusion Material Irradiation Facility/Engineering Validation and Engineering Design Activity (IFMIF/EVEDA) Project. In March 2009, the Administration and Research Building was completed, and the other research facilities; CSC&REC Building, DEMO R&D Building and IFMIF/EVEDA Accelerator Building will be completed in March 2010. In this presentation, the specifications and construction schedule of the individual research buildings will be presented, especially special features of the IFMIF/EVEDA Accelerator Building.

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

http://www.pasj.jp/web_publish/pasj6/papers/tpopa26.pdf

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.

Effect of decontamination factor on core neutronic design of light water reactors using recovered uranium reprocessed by advanced aqueous method

Nakano, Yoshihiro; Okubo, Tsutomu; Koma, Yoshikazu

Journal of Nuclear Science and Technology, 46(5), p.436 - 442, 2009/05

https://doi.org/10.3327/jnst.46.436

In the case where uranium recovered by an advanced aqueous reprocessing is utilized in light water reactors (LWRs), the effects of the decontamination factor (DF) of the reprocessing on core neutronic characteristics were examined. The amounts of transuranium (TRU) elements and fission products (FP) contained in the recovered uranium depend on the DF of the reprocessing process, and also U is generated by neutron capture of U. These all act as poisons in the fuel. Therefore, in this paper, the additional U enrichment necessary to compensate for the produced TRU, FP and U was evaluated for three cases of representative DF values: 10, 10 and infinity. The low value, 10, corresponds to the advanced aqueous reprocessing process investigated here. An APWR core with a discharge burnup of 49 GWd/t when the initial U enrichment is 4.6% was considered as the reference core. It was calculated that the recovered uranium has to be re-enriched up to 5.24% even when DF is infinity in order to achieve the same burnup of 49 GWd/t as the reference core. On the other hand, it was also found that the necessary U enrichment after the advanced aqueous reprocessing studied here with the low DF value 10 is only slightly different. The effect of the DF value on moderator reactivity coefficient was also studied, and no effect was found.

Physical Property Evaluation Testing of Cement-Solidified Products Prepared from Simulated Liquid Waste

Kubo, Yoshikazu*; Sasaki, Tadashi*

JNC TJ8430 2005-003, 91 Pages, 2005/02

JNC-TJ8430-2005-003.pdf:0.64MB

In the low level radioactive waste treatment facility (LWTF), the cement solidification process is being studied on its applicability as a method for preparing waste packages from sodium-nitrate-containing low-level liquid waste generated at reprocessing plants. Solidification of nitrate solution waste: Solidification in a high temperature caused a rapid hydration reaction of cement, resulting in rapid hardening during the mixing process and a drop in fluidity. However, it has been confirmed that liquid waste can be solidified at 80C or so by adding a dispersing agent to improve fluidity and changing the amount of hardening solution to be added for cement hardening. This has verified that the cement solidification process under contemplation is applicable to nitrate-containing liquid waste. Solidification of slurry waste: In solidifying slurry waste, a fall in fluidity and a fall in compressive strength were observed. It is considered that this is attributed to the effects of phosphate contained in the liquid waste. In the case of slurry waste whose phosphate concentration is adjusted to 0g/L, it has been verified that solidified products whose salt mixing ratio is 50wt% can be prepared when the liquid waste temperature is 80C and the degree of concentration is 65wt%. It has been revealed that increases in the NaNO, NaHCO, and NaSO contents cause a delay in cement hardening, a fall in compressive strength, and a fall in fluidity, respectively. It has also been revealed that when liquid waste containing phosphate alone is solidified, solidified products whose salt mixing ratio is 50wt% in terms of hydrate salt (NaPO 8HO) (26.6wt% in terms of anhydrate salt) can be prepared.

Acoustic emission and disturbances in central solenoid model coil for international thermonuclear experimental reactor

Arai, K.*; Ninomiya, Akira*; Ishigooka, Takeshi*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Vieira, R.*; Martovetsky, N.*; Sborchia, C.*; Alekseev, A.*; et al.

Cryogenics, 44(1), p.15 - 27, 2004/01

https://doi.org/10.1016/j.cryogenics.2003.07.006

no abstracts in English

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

https://doi.org/10.1088/0029-5515/41/5/319

no abstracts in English

Present status of JT-60SU design

; Ushigusa, Kenkichi; Kikuchi, Mitsuru; Nagashima, Keisuke; Neyatani, Yuzuru; Miya, Naoyuki; ; Takahashi, Yoshikazu; Hayashi, Takumi; Kuriyama, Masaaki; et al.

Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 1, p.233 - 236, 1998/00

no abstracts in English

Design outline of the accelerator prototype building for the IFMIF/EVEDA project

Kubo, Takashi; Okumura, Yoshikazu; Ohira, Shigeru; Maebara, Sunao; Sakaki, Hironao; Onishi, Seiki; Yonemoto, Kazuhiro; Kojima, Toshiyuki; Garin, P.*; Sugimoto, Masayoshi; et al.

no journal, , 

The Accelerator Prototype Building for the IFMIF/EVEDA Project, in which enforce the engineering validation of the Accelerator, will be constructed in the BA site at Rokkasho-mura, Aomori-ken. Before detail design started, Japan and EU implementing agencies concluded the Procurement Arrangement based on agreed basic design. The building length is about 58 m east-west and about 37 m north-south. The area is about 2,020 m. The Accelerator Vault is center of north and south. RF and electric system are in north of the Vault, and HVAC and cooling water system are in south of the Vault. The control room is put in northwest of the building. Shielding design is based on the evaluation estimated by experts of Japan and EU. The Accelerator will accelerate deuteron to approximately 125 mA and 10 MeV, so the Accelerator Vault is covered with 1.5 m thickness normal concrete shield to protect radiation. To protect neutron streaming, the RF wave guides are through the underground pit into the Vault.

Present status of Japanese tasks for the IFMIF/EVEDA accelerator system

Shinto, Katsuhiro; Ohira, Shigeru; Kikuchi, Takayuki; Kubo, Takashi; Yonemoto, Kazuhiro; Kasuya, Kenichi; Maebara, Sunao; Takahashi, Hiroki; Kojima, Toshiyuki; Tsutsumi, Kazuyoshi; et al.

no journal, , 

no abstracts in English