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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：7.07(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.
Goto, Minoru; Demachi, Kazuyuki*; Ueta, Shohei; Nakano, Masaaki*; Honda, Masaki*; Tachibana, Yukio; Inaba, Yoshitomo; Aihara, Jun; Fukaya, Yuji; Tsuji, Nobumasa*; et al.
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.507 - 513, 2015/09
A concept of a plutonium burner HTGR named as Clean Burn, which has a high nuclear proliferation resistance, had been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to enhance the safety, we propose to introduce PuO-YSZ TRISO fuel with ZrC coating to the Clean Burn. In this study, we conduct fabrication tests aiming to establish the basic technologies for fabrication of PuO-YSZ TRISO fuel with ZrC coating. Additionally, we conduct a quantitative evaluation of the security for the safety, a design of the fuel and the reactor core, and a safety evaluation for the Clean Burn to confirm the feasibility. This study is conducted by The University of Tokyo, Japan Atomic Energy Agency, Fuji Electric Co., Ltd., and Nuclear Fuel Industries, Ltd. It was started in FY2014 and will be completed in FY2017, and the first year of the implementation was on schedule.
Pikuz, T. A.; Faenov, A.*; Fukuda, Yuji; Kando, Masaki; Bolton, P.; Mitorfanov, A.*; Vinogradov, A.*; Nagasono, Mitsuru*; Ohashi, Haruhiko*; Yabashi, Makina*; et al.
Physica Status Solidi (C), 9(12), p.2239 - 2242, 2012/12
Times Cited Count：1 Percentile：50.26(Materials Science, Multidisciplinary)Pikuz, T. A.; Faenov, A.*; Fukuda, Yuji; Kando, Masaki; Bolton, P.; Mitorfanov, A.*; Vinogradov, A.*; Nagasono, Mitsuru*; Ohashi, Haruhiko*; Yabashi, Makina*; et al.
Optics Express (Internet), 20(4), p.3424 - 3433, 2012/02
Times Cited Count：30 Percentile：77.01(Optics)Inogamov, N. A.*; Anisimov, S. I.*; Petrov, Y. V.*; Khokhlov, V. A.*; Zhakhovskii, V. V.*; Faenov, A. Ya.*; Pikuz, T. A.; Fortov, V. E.*; Skobelev, I. Y.*; Kato, Yoshiaki*; et al.
Journal of Optical Technology, 78(8), p.473 - 480, 2011/08
Times Cited Count：6 Percentile：31.13(Optics)Inogamov, N. A.*; Faenov, A. Ya.*; Zhakhovsky, V. V.*; Pikuz, T. A.*; Skobelev, I. Yu.*; Petrov, Y. V.*; Khokhlov, V. A.*; Shepelev, V. V.*; Anisimov, S. I.*; Fortov, V. E.*; et al.
Contributions to Plasma Physics, 51(5), p.419 - 426, 2011/06
Times Cited Count：20 Percentile：60.43(Physics, Fluids & Plasmas)Warm dense matter, arising under the action of ultrashort EUV-FEL pulse onto LiF dielectric crystal, is characterized by high temperature of conduction electrons, with their number density achieving values of the order of atom number density at maximum laser fluences in our experiments. Expansion of matter, heated and pressurized through the electron-ion energy exchange, gives rise to the spallative ablation at small fluences and gaseous outflow from a target in the case of large fluences. Ablation threshold is low in comparison with a longer nanosecond XRL.
-dioctylacetamide) (MIDOA), a new tridentate extractant for technetium(VII), rhenium(VII), palladium(II), and plutonium(IV)Sasaki, Yuji; Ozawa, Masaki; Kimura, Takaumi; Ohashi, Kozaburo*
Solvent Extraction and Ion Exchange, 27(3), p.378 - 394, 2009/05
Times Cited Count：42 Percentile：70.46(Chemistry, Multidisciplinary)2,2'-(Methylimino)bis(-dioctylacetamide) (MIDOA) was developed as a new extractant for Tc-extraction. MIDOA has a similar backbone to TODGA, 
-tetraoctyl-diglycolamimde, the nitrogen atom bonded with methyl group is introduced, instead of ether oxygen in TODGA. MIDOA has a high lipophilic property and is ready to use in the HNO
-
-dodecane extraction system. Tc(VII), Cr(VI), Re(VII), Mo(VI), W(VI), Pd(II) and Pu(IV) are well-extracted by MIDOA. The 
(Tc) values decrease gradually with HNO, H
, and NO
concentrations, and log vs. log [MIDOA] relation supports the species extracted to be 1:1 metal-ligand complex. It is clear that MIDDA (2,2'-(Methylimino)bis(-didodecylacetamide)) and IDDA (2,2'-(Imino)bis(-didodecylacetamide)), which show analogous structures with MIDOA, have similar extraction behavior to that of MIDOA.
Otsuki, Ryusei*; Nasu, Shoichi*; Matsushita, Masaki*; Fujii, Kimio; Ohashi, Kentaro*; Yamamoto, Ryoichi*
Funtai Oyobi Fummatsu Yakin, 51(8), p.633 - 634, 2004/08
We examined effects of deposition temperatures and collector radii onthe yields of fullerenes by arc discharge. Yields of fullerenes were 7-10%, 4-6% and 0.5-1% in the liquid nitrogen-cooling, water-cooling, non-cooling, respectively, and were better with a collector radius of 50mm than with that of 30mm. The weight ratios of C
/C
are about one for all runs of experiments.
Yoshida, Junya; Ohashi, Masaki*; Goto, Ryosuke*; Nagase, Yuichi*; Murai, Rina*; May, S.*; Aye, M. M. T.*; Kimbara, Shinji*; Yoshimoto, Masahiro*; Nakazawa, Kazuma*
no journal, ,
J-PARC E07 collaboration has been performed K- beam exposure to all the emulsion sheet detector. The analysis for double strangeness nuclei is ongoing. We'll discuss the current status, performance, speed, and future prospects.
Faenov, A.*; Pikuz, T. A.; Fukuda, Yuji; Tanaka, Momoko; Kishimoto, Maki; Ishino, Masahiko; Nishikino, Masaharu; Kando, Masaki; Kawachi, Tetsuya; Nagasono, Mitsuru*; et al.
no journal, ,
Ueta, Shohei; Aihara, Jun; Mizutani, Yoshitaka; Ohashi, Hirofumi; Sakaba, Nariaki; Tachibana, Yukio; Honda, Masaki*; Tanaka, Hideki*; Furihata, Noboru*
no journal, ,
In the small-sized high temperature gas-cooled reactor, the improved fuel of which the burnup is designed over 100 GWd/t is used in order to upgrade economy and to decrease radioactive waste. On the other hand, to attain over three times higher burnup than that of a conventional HTTR fuel, 33 GWd/t, researches and developments of the fuel should be needed with regards to the design preventing the fuel from the failure by internal pressure due to gases in the coated fuel particle, the technologies for fabrication of the improved fuel, and the irradiation test to confirm its integrity under the irradiation. A design work, fabrication tests and a plan of the irradiation test for the improved fuel in order to demonstrate the performance are reported.
Pikuz, T. A.; Faenov, A.*; Fukuda, Yuji; Tanaka, Momoko; Ishino, Masahiko; Hasegawa, Noboru; Nishikino, Masaharu; Ohashi, Haruhiko*; Yabashi, Makina*; Tono, Kensuke*; et al.
no journal, ,
