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Journal Articles

Hybrid process combining solvent extraction / low pressure loss extraction chromatography for a reasonable MA(III) recovery process

Sano, Yuichi; Sakamoto, Atsushi; Miyazaki, Yasunori; Watanabe, So; Morita, Keisuke; Emori, Tatsuya; Ban, Yasutoshi; Arai, Tsuyoshi*; Nakatani, Kiyoharu*; Matsuura, Haruaki*; et al.

Proceedings of International Conference on Nuclear Fuel Cycle; Sustainable Energy Beyond the Pandemic (GLOBAL 2022) (Internet), 4 Pages, 2022/07

We developed a hybrid MA(III) recovery process combining MA(III)+Ln(III) co-recovery flowsheet by solvent extraction with TBP and MA(III)/Ln(III) separation flowsheet by simulated moving bed chromatography using HONTA impregnated adsorbents with large particle size porous silica support.

Journal Articles

Magnetically induced electric polarization in Ba$$_{3}$$Fe$$_{2}$$O$$_{5}$$Cl$$_{2}$$ with tunable direction in three dimensions

Abe, Nobuyuki*; Shiozawa, Shunsuke*; Matsuura, Keisuke*; Sagayama, Hajime*; Nakao, Akiko*; Ohara, Takashi; Tokunaga, Yusuke*; Arima, Takahisa*

Physical Review B, 101(18), p.180407_1 - 180407_5, 2020/05

 Times Cited Count:2 Percentile:13.29(Materials Science, Multidisciplinary)

Journal Articles

Nuclear and thermal feasibility of lithium-loaded high temperature gas-cooled reactor for tritium production for fusion reactors

Goto, Minoru; Okumura, Keisuke; Nakagawa, Shigeaki; Inaba, Yoshitomo; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*

Fusion Engineering and Design, 136(Part A), p.357 - 361, 2018/11

 Times Cited Count:3 Percentile:53.26(Nuclear Science & Technology)

A High Temperature Gas-cooled Reactor (HTGR) is proposed as a tritium production device, which has the potential to produce a large amount of tritium using $$^{6}$$Li(n,$$alpha$$)T reaction. In the HTGR design, generally, boron is loaded into the core as a burnable poison to suppress excess reactivity. In this study, lithium is loaded into the HTGR core instead of boron and is used as a burnable poison aiming to produce thermal energy and tritium simultaneously. The nuclear characteristics and the fuel temperature were calculated to confirm the feasibility of the lithium-loaded HTGR. It was shown that the calculation results satisfied the design requirements and hence the feasibility was confirmed for the lithium-loaded HTGR, which produce thermal energy and tritium.

Journal Articles

Magnetic excitations in the orbital disordered phase of MnV$$_2$$O$$_4$$

Matsuura, Keisuke*; Sagayama, Hajime*; Uehara, Amane*; Nii, Yoichi*; Kajimoto, Ryoichi; Kamazawa, Kazuya*; Ikeuchi, Kazuhiko*; Ji, S.*; Abe, Nobuyuki*; Arima, Takahisa*

Physica B; Condensed Matter, 536, p.372 - 376, 2018/05

 Times Cited Count:2 Percentile:10.5(Physics, Condensed Matter)

Journal Articles

Spin-orbital correlated dynamics in the spinel-type vanadium oxide MnV$$_{2}$$O$$_{4}$$

Matsuura, Keisuke*; Sagayama, Hajime*; Uehara, Amane*; Nii, Yoichi*; Kajimoto, Ryoichi; Kamazawa, Kazuya*; Ikeuchi, Kazuhiko*; Ji, S.*; Abe, Nobuyuki*; Arima, Takahisa*

Physical Review Letters, 119(1), p.017201_1 - 017201_6, 2017/07

 Times Cited Count:12 Percentile:66.58(Physics, Multidisciplinary)

Journal Articles

Structural investigation of thorium in molten lithium-calcium fluoride mixtures for salt treatment process in molten salt reactor

Numakura, Masahiko*; Sato, Nobuaki*; Bessada, C.*; Okamoto, Yoshihiro; Akatsuka, Hiroshi*; Nezu, Atsushi*; Shimohara, Yasuaki*; Tajima, Keisuke*; Kawano, Hirokazu*; Nakahagi, Takeshi*; et al.

Progress in Nuclear Energy, 53(7), p.994 - 998, 2011/11

 Times Cited Count:13 Percentile:69.86(Nuclear Science & Technology)

X-ray absorption fine structure (XAFS) measurements on thorium fluoride in molten lithium-calcium fluoride mixtures and molecular dynamics (MD) simulation of zirconium and yttrium fluoride in molten lithium-calcium fluoride mixtures have been carried out. In the molten state, coordination number of thorium and inter ionic distances between thorium and fluorine in the first neighbor are nearly constant in all mixtures. However the fluctuation factors (Debye-Waller factor and C$$_3$$ cumulant) increase until $$x$$CaF$$_2$$ = 0.17 and decrease by addition of excess CaF$$_2$$. It means that the local structure around Th$$^{4+}$$ is disordered until $$x$$CaF$$_2$$=0.17 and stabilized over $$x$$CaF$$_2$$ = 0.17. The variation of fluctuation factors is related to the number density of F$$^-$$ in ThF$$_4$$ mixtures and the stability of local structure around Th$$^{4+}$$ increases with decreasing the number density of F$$^-$$ in ThF$$_4$$ mixtures. This tendency is common to those in the ZrF$$_4$$ and YF$$_3$$ mixtures.

Journal Articles

Mechanisms of reduction in hole concentration in Al-implanted p-type 6H-SiC by 1 MeV electron irradiation

Matsuura, Hideharu*; Izawa, Keisuke*; Minohara, Nobumasa*; Oshima, Takeshi

Japanese Journal of Applied Physics, 47(7), p.5355 - 5357, 2008/07

 Times Cited Count:2 Percentile:9.83(Physics, Applied)

The reduction in hole concentration ($$p$$) in Al-implanted $$p$$-type 6H-SiC due to 1 MeV electron irradiation was studied. By analysis of $$p$$, the acceptor density ($$N_{A}$$), its ionizing energy ($$E_{A}$$) and nature of the acceptor are determined. As a result, the acceptor observed in this study is assigned to an Al acceptor. $$E_{A}$$ is independent of irradiation fluence ($$Phi$$), in spite that $$N_{A}$$ is strongly dependent on $$Phi$$. We derived an analytical expression for the fluence dependence of $$N_{A}$$ and we estimated the removal coefficient (i.e., removal cross-section) of $$N_{A}$$ to be 6.4$$times$$10$$^{18}$$ cm$$^{2}$$ for 1 MeV electron irradiation. The reduction in p due to electron irradiation is found to be mainly due to the decrease in $$N_{A}$$, not to the increase in the density of defects with deep-level, because the decrease in $$N_{A}$$ is much larger than the increment in the density of deep-level defects.

JAEA Reports

Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.

JAERI-Research 2004-008, 383 Pages, 2004/06

JAERI-Research-2004-008.pdf:21.49MB

The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.

Oral presentation

Changes of acceptor density in Al-doped 6H-SiC epilayer by 200 keV electron irradiation

Yanagisawa, Hideki*; Izawa, Keisuke*; Matsuura, Hideharu*; Oshima, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Polarised neutron spectrometer, POLANO, at J-PARC attempts at understanding novel magnetism

Oyama, Kenji*; Yokoo, Tetsuya*; Ito, Shinichi*; Suzuki, Junichi*; Iwasa, Kazuaki*; Sato, Taku*; Kira, Hiroshi*; Sakaguchi, Yoshifumi*; Ino, Takashi*; Oku, Takayuki; et al.

no journal, , 

Oral presentation

Evaluation of nuclear characteristics of lithium loaded HTGR for tritium production for fusion reactors

Goto, Minoru; Okumura, Keisuke; Nakagawa, Shigeaki; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*

no journal, , 

A feasibility study of a High Temperature Gas-cooled Reactor (HTGR) for tritium production using $$^{6}$$Li(n,$$alpha$$)T reaction for fusion reactors has been conducted. In this study, the burn-up chain was modified to treat $$^{6}$$Li(n,a)T reaction directory in neutronics calculations, and then the feasibility study was performed from the view point of nuclear characteristics using SRAC code system, which has experience in neutronics analysis of HTGRs.

Oral presentation

Evaluation of nuclear and thermal characteristics of lithium loaded HTGR for tritium production

Goto, Minoru; Okumura, Keisuke; Nakagawa, Shigeaki; Inaba, Yoshitomo; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*

no journal, , 

A feasibility study of a High Temperature Gas-cooled Reactor (HTGR) for tritium production using $$^{6}$$Li(n,$$alpha$$)T reaction for fusion reactors has been conducted. In this study, the burn-up chain was modified to treat $$^{6}$$Li(n,$$alpha$$)T reaction directory in neutronics calculations, and then the feasibility study was performed from the view point of nuclear and thermal characteristics using SRAC code system, which has experience in neutronics analysis of HTGRs.

12 (Records 1-12 displayed on this page)
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