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Journal Articles

Spontaneous topological Hall effect induced by non-coplanar antiferromagnetic order in intercalated van der Waals materials

Takagi, Hirotaka*; Takagi, Rina*; Minami, Susumu*; Nomoto, Takuya*; Oishi, Kazuki*; Suzuki, Michito*; Yanagi, Yuki*; Hirayama, Motoaki*; Khanh, N.*; Karube, Kosuke*; et al.

Nature Physics, 19(7), p.961 - 968, 2023/07

 Times Cited Count:50 Percentile:99.07(Physics, Multidisciplinary)

Journal Articles

Sodium-cooled Fast Reactors

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.

Journal Articles

Fabrication and short-term irradiation behaviour of Am-bearing MOX fuels

Kihara, Yoshiyuki; Tanaka, Kosuke; Koyama, Shinichi; Yoshimochi, Hiroshi; Seki, Takayuki; Katsuyama, Kozo

NEA/NSC/R(2017)3, p.341 - 350, 2017/11

In order to investigate the effect of the addition of americium to MOX fuels on the irradiation behaviour, the "Am-1" program is being conducted at the JAEA. The Am-1 program consists of two short-term irradiation tests of 10-min and 24-h irradiation periods, and a steady-state irradiation test. The short-term irradiation tests and their post irradiation examinations (PIEs) have been successfully completed. To date, the data for PIE of the Am-MOX fuels focused on the microstructural evolution and redistribution behaviour of Am at the initial stage of irradiation have been obtained and reported. In this paper, the results obtained from the Am-1 program are reviewed and detailed descriptions of the fabrication and inspection techniques for the Am-MOX fuels prepared for the program are provided. PIE data for the Am-MOX fuels at the initial stage of irradiation have been accumulated. In this paper, unpublished PIE data for the Am-MOX fuels are also presented.

Journal Articles

Development of multi-colored neutron talbot-lau interferometer with absorption grating fabricated by imprinting method of metallic glass

Seki, Yoshichika; Shinohara, Takenao; Parker, J. D.*; Yashiro, Wataru*; Momose, Atsushi*; Kato, Kosuke*; Kato, Hidemi*; Sadeghilaridjani, M.*; Otake, Yoshie*; Kiyanagi, Yoshiaki*

Journal of the Physical Society of Japan, 86(4), p.044001_1 - 044001_5, 2017/03

 Times Cited Count:14 Percentile:64.96(Physics, Multidisciplinary)

For the effective phase imaging at pulsed neutron sources, we have designed and developed the multi-colored Talbot-Lau interferometer which works at several wavelengths. At the Energy Resolved Neutron Imaging System RADEN in J-PARC, we demonstrated its operation by observing the visibilities of moire fringes derived from different wavelengths (0.25, 0.50, and 0.75 nm). We also investigated the variation of moire fringes dependent on the wavelength resolution from 18% to 50% and showed the advantage of pulsed beams. At the central wavelength of 0.5 nm, we have succeeded in interferometric imaging for the samples of metal rods made of aluminum, lead, and copper. An absorption grating as an analyzer was fabricated by imprinting of metallic glass for the first time, and showed a clear moire fringe with the high visibility of 68% and a well-controlled shape in comparison with previous ones fabricated by oblique evaporation of gadolinium.

JAEA Reports

Evaluation of fission product and actinide release behaviors focusing on their chemical forms; Phase relation and fission product release behavior resulting from interaction between molten zircaloy and irradiated MOX fuel

Tanaka, Kosuke; Miwa, Shuhei; Sato, Isamu; Hirosawa, Takashi; Sekine, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*; Obayashi, Hiroshi; Koyama, Shinichi

JAEA-Research 2013-022, 62 Pages, 2014/01

JAEA-Research-2013-022.pdf:33.64MB

In order to establish the method for heating tests focused on the fission product release resulting from the high temperature chemical interaction between fuel and cladding material and to obtain the novel data on fission product release behaviors, the heating test was carried out with irradiate MOX fuel pellet and cladding.

Journal Articles

Study of an electromagnetic pump applied to a primary main pumps of a large scale sodium cooled reactor

Aizawa, Kosuke; Kotake, Shoji; Chikazawa, Yoshitaka; Ara, Kuniaki; Araseki, Hideo*; Aizawa, Rie*; Ota, Hiroyuki*

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9402_1 - 9402_8, 2009/05

This paper describes a future innovative design options with a parallel electromagnetic pump (EMP) system as the main circulating pump of the JSFR design. A conceptual design of EMPs integrated with an intermediate heat exchanger (IHX) is carried out. The major design parameters are consistent with the current JSFR design, where the main flow rate is 630 m$$^{3}$$/min and the flow halving time is the same of the mechanical pump with the similar reliability. As a result of several design studies, a five parallel EMPs with IHX system has been selected from the geometry suitability for JSFR design. The EMP advantages comparing with mechanical pumps are investigated from the views of in-service inspection, maintenance and reliability. Numerical analysis with two dimensional MHD codes is conducted on a former experiment of a 160 m$$^{3}$$/min flow rate EMP. The overall trend of the experimental data and the numerical results agrees with that in small-scale EMPs.

Journal Articles

Unsteady motion of parastic-capillary ripples on the gravity waves

Seki, Kosuke*; Tsuji, Yoshiyuki*; Kondo, Masaya; Kukita, Yutaka*

Nihon Kikai Gakkai 2001-Nendo Nenji Taikai Koen Rombunshu, p.9 - 10, 2001/00

no abstracts in English

Oral presentation

Thermal conductivity of inert matrix fuels using the asbestos waste-derived ceramics as a sintering additive

Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*

no journal, , 

Thermal conductivies of MgO-based inert matrix fuels containing PuO$$_{2}$$ using the asbestos waste-derived ceramics as a sintering additive were experimentally investigated. Thermal diffusivities of fuels were measured by laser flush method. The effects of the MgO-SiO$$_{2}$$ compound additives addition on the thermal conductivity were discussed.

Oral presentation

Evaluation of fission products migration behavior by fuel heating tests, 2; Phase status of the heated fuel sample

Tanaka, Kosuke; Miwa, Shuhei; Sato, Isamu; Hirosawa, Takashi; Sekine, Shinichi; Obayashi, Hiroshi; Koyama, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*

no journal, , 

In order to develop the heating method for both fuel pellet and cladding, irradiated MOX fuel together with Zry-2 cladding were heated by using source term evaluation equipment.

Oral presentation

Evaluation of fission products migration behavior by fuel heating tests, 3; Release behavior of fission products from the heated fuel sample

Sato, Isamu; Hirosawa, Takashi; Miwa, Shuhei; Tanaka, Kosuke; Koyama, Shinichi; Tokoro, Daishiro*; Seki, Takayuki*

no journal, , 

Fuel pellets irradiated in the advanced thermal reactor, "FUGEN", were heated using a high frequency induction fuenace, and then the release and residue behavior of fission products were observed.

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 2; Effects of a control material of boron for FP transport behavior

Sato, Isamu; Onishi, Takashi; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Ishigamori, Toshio*; Seki, Takayuki*; Shinada, Masanori*; et al.

no journal, , 

As a material simulating FP, CsI was heated and evaporated to be decomposited on the surface of a tube having a temperature gradient. Gaseous B$$_{2}$$O$$_{3}$$ made by heating it at higher temperature was react with CsI decomposited on the surface, and then the boron effects for decomposition and migration behavior of Cs and I were observed. Consequently, it was indicated that boron vapor could strip decomposited CsI to make it gaseous species again and then the guseous CsI could move to the colder position.

Oral presentation

Fabrication of Am-doped MgO advanced fuel for use in fast reactor

Miwa, Shuhei; Osaka, Masahiko; Tanaka, Kosuke; Ishi, Yohei; Tanaka, Kenya; Sekine, Shinichi*; Seki, Takayuki*

no journal, , 

R&D of advanced fuel containing minor actinide for use in fast reactors is described related to the composite fuel with MgO matrix. Fabrication tests of MgO composite fuels containing Am were done by a practical process that could be adapted to the presently used commercial manufacturing technology. Am-containing MgO composite fuels having good characteristics, i.e., having no defects, a high density, a homogeneous dispersion of host phase, were obtained.

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 5; Technical development of fuel heating under a multiple of atmosphere

Hirosawa, Takashi; Sato, Isamu; Tanaka, Kosuke; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Ishigamori, Toshio*; Seki, Takayuki*

no journal, , 

In order to demonstrate severe accident condition on BWR, FP gas release test device was alternated to be used under oxidizing atmosphere. As a result, it is confirmed that the oxidation reaction of tungsten part was inhibited under high temperature.

Oral presentation

Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents, 4; Outline and main results

Tanaka, Kosuke; Seki, Takayuki; Oka, Hiroshi; Matsuda, Tetsushi*; Muta, Hiroaki*; Sekioka, Ken*; Tokoro, Daishiro*

no journal, , 

The outline and main results of "Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents", entrusted by the Ministry of Education, Culture, Sports, Science and Technology of Japan are presented.

Oral presentation

Development of pulsed neutron imaging techniques at RADEN

Shinohara, Takenao; Kai, Tetsuya; Oikawa, Kenichi; Nakatani, Takeshi; Hiroi, Kosuke; Su, Y. H.; Hayashida, Hirotoshi*; Parker, J. D.*; Matsumoto, Yoshihiro*; Zhang, S.*; et al.

no journal, , 

no abstracts in English

Oral presentation

Current status of the energy-resolved neutron imaging system RADEN

Shinohara, Takenao; Kai, Tetsuya; Oikawa, Kenichi; Segawa, Mariko; Nakatani, Takeshi; Hiroi, Kosuke; Su, Y. H.; Hayashida, Hirotoshi*; Matsumoto, Yoshihiro*; Parker, J. D.*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of energy-resolved neutron imaging at RADEN in J-PARC MLF

Shinohara, Takenao; Kai, Tetsuya; Oikawa, Kenichi; Hiroi, Kosuke; Su, Y. H.; Nakatani, Takeshi; Seki, Yoshichika; Tsuchikawa, Yusuke; Hayashida, Hirotoshi*; Parker, J. D.*; et al.

no journal, , 

The Energy-Resolved Neutron Imaging System, RADEN, in the Materials and Life Science Experimental Facility (MLF) of J-PARC, has been constructed as the world's first dedicated instrument to the pulsed neutron imaging. RADEN is designed to conduct energy-resolved neutron imaging experiments like Bragg edge, resonance absorption and pulsed polarized neutron imaging by fully utilizing the short-pulsed neutron's nature, together with the conventional neutron radiography and tomography. The construction of RADEN was completed in 2014, and user operation was started from April 2015 after commissioning studies using the neutron beam. In addition to the user programs, the instrument group continues further technical developments for advanced energy-resolved neutron imaging and improving the performance of devices, especially the counting type imaging detectors.

Oral presentation

Thermophysical properties of complex uranium or plutonium oxides with alkaline-earth metals

Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Seki, Takayuki*; Kashimura, Naoki*; Kurosaki, Ken*; Tokushima, Kazuyuki*; Muta, Hiroaki*; Oishi, Yuji*; Yamanaka, Shinsuke*

no journal, , 

Complex uranium or plutonium oxides with alkaline-earth metals were prepared by using conventional powder metallurgy and its thermophysical properties were evaluated.

Oral presentation

Current status of the energy-resolved neutron imaging system "RADEN"

Shinohara, Takenao; Kai, Tetsuya; Oikawa, Kenichi; Nakatani, Takeshi; Segawa, Mariko; Hiroi, Kosuke; Su, Y. H.; Ueno, Wakana; Seki, Yoshichika; Hayashida, Hirotoshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Present status of the energy-resolved neutron imaging system, RADEN, in J-PARC

Shinohara, Takenao; Kai, Tetsuya; Oikawa, Kenichi; Hiroi, Kosuke; Su, Y. H.; Segawa, Mariko; Nakatani, Takeshi; Hayashida, Hirotoshi*; Matsumoto, Yoshihiro*; Parker, J. D.*; et al.

no journal, , 

28 (Records 1-20 displayed on this page)