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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：8 Percentile：96.03(Physics, Multidisciplinary)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.
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 In this paper, unpublished PIE data for the Am-MOX fuels are also presented.
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：13 Percentile：66.28(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.
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.
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
/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/min flow rate EMP. The overall trend of the experimental data and the numerical results agrees with that in small-scale EMPs.
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
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.
Ochiai, Kentaro; Sato, Satoshi; Takakura, Kosuke; Yamauchi, Michinori*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Seki, Masakazu; Kawabe, Masaru*; Konno, Chikara; et al.
no journal, ,
The test blanket module (TBM), water cooled pebble bed type, which is to be installed in ITER has been designed in JAEA. The TBM is made up of water cooling system with a kind of low activation ferrite, beryllium as neutron breeder, 
Li enriched Li
TiO
or LiO pebble as tritium breeding material. To evaluate the nuclear properties, we have carried out some DT neutronics experiments with TBM mock up assemblies in the Fusion Neutronics Source (FNS) and one of the TBM nuclear properties, the tritium production rate (TPR), in the LiTiO layer has been clarified by means of a liquid scintillation counter method with LiCO pellets or LiO pebbles.
Miwa, Shuhei; Osaka, Masahiko; Tanaka, Kosuke; Seki, Takayuki*
no journal, ,
For the evaluation of phase relation and irradiation behavior of low-decontaminated fuel and heterogeneous fuel, the oxygen potential of (Pu
Am
Nd
)O was investigated by the thermogravity analysis in various atmospheres which was adjusted by changing the ratio of HO/H, CO/H and dilution ratio of O.
Miwa, Shuhei; Osaka, Masahiko; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Sekine, Shinichi*; Ishida, Takashi*; Seki, Takayuki*; Kashimura, Naoki*
no journal, ,
no abstracts in English
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.
Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*; Kashimura, Naoki*
no journal, ,
no abstracts in English
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 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 compound additives addition on the thermal conductivity were discussed.
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.
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.
Tanaka, Kosuke; Yoshimochi, Hiroshi; Obayashi, Hiroshi; Koyama, Shinichi; Seki, Takayuki*; Shinada, Masanori*
no journal, ,
Oxidation behavior was investigated in Am-containing MOX fuel pellets.
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 BO 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.
Iwasaki, Maho; Tanaka, Kosuke; Sato, Isamu; Miwa, Shuhei; Osaka, Masahiko; Amaya, Masaki; Koyama, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*; Ishigamori, Toshio*
no journal, ,
no abstracts in English
Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Onishi, Takashi; Suto, Mitsuo; Miwa, Shuhei; Osaka, Masahiko; Koyama, Shinichi; Seki, Takayuki*; Shinada, Masanori*; et al.
no journal, ,
In order to evaluate chemical forms of deposited fission products, 
ray spectrometry, macroscopic observation, XRD, ICP-MS analysis were performed in the specimens of sampling parts after a heating test of a fuel which was irradiated at FUGEN.
