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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

Development of fabrication technology of ITER shielding blanket

Enoeda, Mikio

Koon Gakkai-Shi, 30(5), p.256 - 262, 2004/09

Fabrication technologies for ITER in-vessel components, especially the shielding blanket with the separable first wall panel has been developed. Hot Isostatic Pressing (HIP) has been applied to the bonding of Cu-alloy/stainless steel and beryllium/Cu-alloy. First wall mock-ups fabricated by using HIP were tested under high heat fluxes and showed sufficient heat removal and thermal fatigue performance. Water jet and electrical discharge machining have been applied to manufacture slots into the first wall panel and the shield block. With these technologies, a first wall panel prototype and a shielding block 1/2 mock-up were successfully fabricated.

Journal Articles

Validation of minor actinide cross sections by studying samples irradiated for 492 days at the dounreay prototype fast reactor, 2; Burnup calculations

Tsujimoto, Kazufumi; Kono, Nobuaki; Shinohara, Nobuo; Sakurai, Takeshi; Nakahara, Yoshinori; Mukaiyama, Takehiko; Raman, S.*

Nuclear Science and Engineering, 144(2), p.129 - 141, 2003/06

To evaluate neutron cross-section data of minor actinides, separated actinide samples and dosimetry samples were irradiated at the Dounreay Prototype Fast Reactor for 492 effective full power days. Based on the burnup calculations of major actinide and dosimetry samples, the neutron flux distribution and the flux level were adjusted at the locations where minor actinide samples were irradiated. The burnup calculations were carried out for minor actinides using the determined flux distribution and flux level. This paper discusses the burnup calculations and the validation of minor actinide cross-section data in evaluated nuclear data libraries. We find that we can obtain reliable FIMA (fission per initial metallic atom) values by using the $$^{148}$$Nd method except that the uncertainties in the FIMA values are large for $$^{234}$$U, $$^{238}$$Pu, Am isotopes, and Cm isotopes because the $$^{148}$$Nd yields are known poorly for these isotopes and are probably overestimated. For these isotopes, measurements to improve the fission-yield data are needed. We also find that, in general, the JENDL-3.2 nuclear data for the minor actinides are adequate for the conceptual design study of transmutation systems. But, there are some nuclides (especially $$^{238}$$Pu and $$^{242}$$Pu) for which new measurements are needed particulary if the minor actinides constitute a major part of the nuclear fuel.

Journal Articles

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Sako, Kiyoshi*; Takase, Kazuyuki; Seki, Yasushi; Adachi, Junichi*; Yamazaki, Seiichiro*; et al.

Fusion Engineering and Design, 48(3-4), p.271 - 279, 2000/09

 Times Cited Count:14 Percentile:29.65

no abstracts in English

Journal Articles

Current status of the JAERI free electron laser program

Minehara, Eisuke; Nagai, Ryoji; Sawamura, Masaru; Takao, Masaru*; *; Sugimoto, Masayoshi; Sasaki, Shigemi; Okubo, Makio; *; Suzuki, Yasuo; et al.

Proc. of the 5th Japan-China Joint Symp. on Accelerators for Nuclear Science and Their Applications, 0, p.104 - 108, 1993/00

no abstracts in English

Journal Articles

Development of software integration methodology for human-friendly and intelligent nuclear reactor design support system

Araya, Fumimasa; *; *; ;

Proc. of the Joint Int. Conf. on Mathematical Methods and Supercomputing in Nuclear Applications,Vol. 1, p.466 - 476, 1993/00

no abstracts in English

Journal Articles

Performance of the prototype JT-60 injector unit in the presence of a simulated stray magnetic field

; ; ; ; ; ; Matsuda, Shinzaburo; ; ; Ohara, Yoshihiro; et al.

Fusion Technology, 7(3), p.391 - 398, 1985/00

no abstracts in English

JAEA Reports

Extraction of 10sec/75keV/70A Ion Beams at Prototype Neutral Beam Injector Unit for JT-60

; Araki, Masanori; ; ; ; ; ; Matsuda, Shinzaburo; ; *; et al.

JAERI-M 82-045, 13 Pages, 1982/05

JAERI-M-82-045.pdf:0.66MB

no abstracts in English

JAEA Reports

Prototype Inverted Sputter Source for Negative Heavy Ions

; ;

JAERI-M 7303, 12 Pages, 1977/10

JAERI-M-7303.pdf:0.71MB

no abstracts in English

Oral presentation

Progress of research and development for ITER Full-W divertor, 1; Manufacturing full-scale prototypes of plasma facing units and their high heat flux testing

Ezato, Koichiro; Seki, Yohji; Suzuki, Satoshi; Yokoyama, Kenji; Yamada, Hirokazu; Hirayama, Tomoyuki

no journal, , 

no abstracts in English

Oral presentation

Measurement of thermal-hydraulic phenomena under prototype accident conditions

Nakamura, Hideo

no journal, , 

no abstracts in English

11 (Records 1-11 displayed on this page)
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