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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Ueta, Shohei; Mizuta, Naoki; Fukaya, Yuji; Goto, Minoru; Tachibana, Yukio; Honda, Masaki*; Saiki, Yohei*; Takahashi, Masashi*; Ohira, Koichi*; Nakano, Masaaki*; et al.
Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02
Times Cited Count：1 Percentile：12.16(Nuclear Science & Technology)The concept of a plutonium (Pu) burner HTGR is proposed to incarnate highly-effective Pu utilization by its inherent safety features. The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO
) and yttria stabilized zirconia (YSZ) as an inert matrix. This paper presents feasibility study of Pu burner HTGR and R&D on the 3S-TRISO fuel.
Briggs, L.*; Monti, S.*; Hu, W.*; Sui, D.*; Su, G. H.*; Maas, L.*; Vezzoni, B.*; Partha Sarathy, U.*; Del Nevo, A.*; Petruzzi, A.*; et al.
Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.3030 - 3043, 2015/08
The International Atomic Energy Agency Coordinated Research Project, "Benchmark Analyses of an EBR-II Shutdown Heat Removal Test" is in the third year of its four-year term. Nineteen participants representing eleven countries have simulated two of the most severe transients performed during the Shutdown Heat Removal Tests program conducted at Argonne's Experimental Breeder Reactor II. Benchmark specifications were created for these two transients, enabling project participants to develop computer models of the core and primary heat transport system, and simulate both transients. In phase 1 of the project, blind simulations were performed and then evaluated against recorded data. During phase 2, participants have refined their models to address areas where the phase 1 simulations did not predict as well as desired the experimental data. This paper describes the progress that has been made to date in phase 2 in improving on the earlier simulations and presents the direction of planned work for the remainder of the project.
Koizumi, Yasuo; Ohira, Koji*
Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), 14 Pages, 2015/08
In this study, to examine the channel narrowing effect on the two-phase flow boiling heat transfer, single-phase flow and flow boiling heat transfer experiments were performed for a thin rectangular channel of the width W = 3 mm and the height 
= 1.25 mm 
0.163 mm. When the hydraulic diameter became smaller than 1.06 mm, for the single-phase flow conditions, the heat transfer coefficient became smaller than that for a conventional size channel. In the flow boiling, churn flow appeared even at a low heat flux and a flow pattern was mainly the churn flow or/and the annular flow. The critical heat flux was higher than the value of Kutateladze correlation for the pool boiling. However, when the flow channel height became extremely narrow, measured critical heat flux became lower than the Kutateladze value. based on these results, the modification method to incorporate the channel narrowing effect into the heat transfer coefficient correlation was proposed.
Mosnier, A.*; Beauvais, P. Y.*; Branas, B.*; Comunian, M.*; Facco, A.*; Garin, P.*; Gobin, R.*; Gournay, J. F.*; Heidinger, R.*; Ibarra, A.*; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.588 - 590, 2010/05
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.
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.
Kubo, Takashi; Maebara, Sunao; Ohira, Shigeru; Takahashi, Hiroki; Yonemoto, Kazuhiro; Kojima, Toshiyuki; Kikuchi, Takayuki; Sakaki, Hironao; Kimura, Haruyuki; Okumura, Yoshikazu; et al.
no journal, ,
IFMIF/EVEDA Prototype Accelerator Building is a facility for validation of prototype accelerator which will be made for the Engineering Validation and Engineering Design Activity (EVEDA) of the International Fusion Material Irradiation Facility (IFMIF). This building is constructed the International Fusion Energy Research Center in Rokkasho village, Aomori prefecture, as a part of the Broader Approach activity which is an international cooperation between Japan and EU. The detail design was completed in 2007, and its construction work was started in March, 2008. The building is an one story, steel construction. The width of east-west is 58 m, north-south is 37 m, maximum height is 10.95 m, and floor area is 2019.5 m. The Accelerator Vault which made of concrete is in center of the building. The southern side is HVAC and cooling machines room, and the other side is Radio Frequebcy power supply area. Its underground was constructed in 2008, and the Accelerator Vault was constructed in May, 2009. Now, roofing work is doing. The building will be completed in May, 2010.
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
Okamoto, Koji*; Ohashi, Kazutaka*; Ohira, Koichi*; Kunitomi, Kazuhiko
no journal, ,
A plutonium-burner High Temperature Gas-cooled Reactor (HTGR) can be designed to incinerate plutonium with extremely high safety including the nuclear waste. In order to demonstrate this concept, we evaluated security enhanced fuel for the plutonium-burner HTGR and confirmed its feasibility.
