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Minato, Kazuo; Ogawa, Toru
Comprehensive Nuclear Materials, 2nd Edition, Vol.5, p.334 - 360, 2020/08
TRISO coated particle fuel has been developed for the high temperature gas-cooled reactors, which consists of microspherical fuel kernel and coating layers of pyrolytic carbon and silicon carbide. To improve the high temperature stability, the resistance to the chemical attack by fission products and the retention of fission products of the TRISO coated particle fuels, several types of advanced fuels were proposed and tested. Coated particle fuels for fast reactors were also proposed and tested. In this paper, fuel designs, fabrications, characterization techniques and fuel performance of these advanced coated particle fuels are systematically described. This is the updated version of the paper having the same title in Comprehensive Nuclear Materials published in 2012.
Baron, P.*; Cornet, S. M.*; Collins, E. D.*; DeAngelis, G.*; Del Cul, G.*; Fedorov, Y.*; Glatz, J. P.*; Ignatiev, V.*; Inoue, Tadashi*; Khaperskaya, A.*; et al.
Progress in Nuclear Energy, 117, p.103091_1 - 103091_24, 2019/11
Times Cited Count：73 Percentile：94.03(Nuclear Science & Technology)The results of an international review of separation processes for spent nuclear fuel (SNF) recycling in future closed fuel cycles with the evaluation of Technology Readiness Level are reported. This study was made by the Expert Group on Fuel Recycling Chemistry (EGFRC) organised by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD). A unique feature of this study was that processes were classified according to a hierarchy of separations aimed at different elements within spent fuel (uranium; uranium-plutonium co-recovery; minor actinides; high heat generating radionuclides) and also the Head-end processes, used to prepare the SNF for chemical separation, were included. Separation processes covered both wet (hydrometallurgical) and dry (pyro-chemical) processes.
Sasaki, Hirokazu*; Nishikubo, Hideo*; Nishida, Shinsuke*; Yamazaki, Satoshi*; Nakasaki, Ryusuke*; Isomatsu, Takemi*; Minato, Ryuichiro*; Kinugawa, Kohei*; Imamura, Akihiro*; Otomo, Shinya*; et al.
Furukawa Denko Jiho, (138), p.2 - 10, 2019/02
no abstracts in English
Minato, Kazuo
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(6), P. 365, 2018/06
HOTLAB 2017 was held by the Japan Atomic Energy Agency in cooperation with the Atomic Energy Society of Japan and the International Atomic Energy Agency. This series of meetings has been held every year since 1963 to make information exchange and cooperation on post-irradiation examination and remote handling technologies and safe operation of hot laboratories. 155 engineers and researchers from 21 countries (107 from abroad) participated in the meeting. 51 oral presentations and 29 poster presentations were made. During the meeting a lively discussion was made between engineers being involved in installation of new technology and apparatus in hot cells and researchers aiming at using new ones. There was a great expectation in the construction of a new hot laboratory for analyses of the fuel debris of TEPCO's Fukushima Daiichi Nuclear Power Station. The necessity for facilities and apparatus for sophisticated analyses and measurements on small irradiated samples was emphasized.
Tsujimoto, Kazufumi; Arai, Yasuo; Minato, Kazuo
Nihon Genshiryoku Gakkai-Shi ATOMO, 59(11), p.644 - 648, 2017/11
no abstracts in English
Minato, Kazuo; Tsujimoto, Kazufumi; Tanabe, Hiromi*; Fujimura, Koji*
Nihon Genshiryoku Gakkai-Shi ATOMO, 59(8), p.475 - 479, 2017/08
no abstracts in English
Minato, Kazuo
Hokeikyo Nyusu, (56), P. 1, 2015/10
The number of students who study nuclear engineering decreased after the accident at the Fukushima Dai-ichi Nuclear Power Station. Securing human resources and their development should be strongly promoted in cooperation with universities, industry, and research institutes since the universities hardly maintain and operate their nuclear facilities.
Hayashi, Hirokazu; Akabori, Mitsuo; Minato, Kazuo
Journal of Radioanalytical and Nuclear Chemistry, 303(2), p.1331 - 1334, 2015/02
Times Cited Count：0 Percentile：0.01(Chemistry, Analytical)Electrochemical behavior of Am in NaCl-2CsCl melt at 823 K was investigated by transient electrochemical techniques such as cyclic voltammetry and differential pulse voltammetry. The results show that Am(III) ion is reduced to Am metal by a two-step mechanism via Am(II) ion. Formal standard potential of Am(III)/Am(II) and that of Am(II)/Am(0) redox couples have been determined to be -2.73 and -2.97 V vs Cl
/Cl
, respectively.
Minato, Kazuo
Reprocessing and Recycling of Spent Nuclear Fuel, p.565 - 578, 2015/00
This chapter describes the development of closed nuclear fuel cycles in Japan. The chapter first discusses the impact of the severe accident at Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station on the development of the closed nuclear fuel cycles, including establishment of the new nuclear safety regulatory system and revision of the Basic Energy Plan. The chapter then describes requirements for the future nuclear fuel cycle development. Following reviews of nuclear fuel cycle development programs and highlights, the chapter finally discusses the future trends of the development.
Takano, Masahide; Hayashi, Hirokazu; Minato, Kazuo
Journal of Nuclear Materials, 448(1-3), p.66 - 71, 2014/05
Times Cited Count：2 Percentile：16.44(Materials Science, Multidisciplinary)A powder sample of curium nitride (CmN) containing 0.35%-PuN and 3.59%-AmN was prepared by carbothermic nitridation of the oxide. The lattice expansion induced by self-irradiation damage at room temperature was measured as a function of time. The saturated 
a/a
value was 0.43%, which is greater than those for transuranium dioxides available in literature. The undamaged lattice parameter at 297
1 K was determined to be 0.502610.00006 nm. Temperature dependence of the lattice parameter was measured by a high temperature X-ray diffractometer in the temperature range up to 1375 K. The linear thermal expansion of the lattice from 293 to 1273 K is 0.964% and the corresponding thermal expansion coefficient is 9.84 
10
K
. Comparing with the other actinide nitrides, it was found that CmN lies between the higher expansion nitrides (PuN and AmN) and the lower expansion nitrides (UN and NpN).
Hayashi, Hirokazu; Takano, Masahide; Kurata, Masaki; Minato, Kazuo
Journal of Nuclear Materials, 440(1-3), p.477 - 479, 2013/09
Times Cited Count：5 Percentile：38.62(Materials Science, Multidisciplinary)Neptunium trichloride of high purity was synthesized by the solid-state reaction of neptunium nitride, which was prepared from the oxide by the carbothermic reduction method, and cadmium chloride in a similar manner as reported for synthesis of AmCl
. Lattice parameters of hexagonal NpCl were determined from the X-ray diffraction pattern to be a = 0.7421 0.0006 nm and c = 0.4268 0.0003 nm, which fairly agree with the reported values (a = 0.742 0.001 nm and c = 0.4281 0.0005 nm). Melting temperature of NpCl was measured with about 1 mg of the sample which was hermetically encapsulated in a gold crucible using a differential thermal analyzer with heating and cooling rate of 10 K/min in an argon gas flow (50 mL/min). The melting temperature of NpCl was determined to 1070 3 K, which is close to the recommended value 107530 K, which was derived from the mean value of the melting temperature for UCl(1115K) and that for PuCl (1041 K).
Hayashi, Hirokazu; Hagiya, Hiromichi; Kim, S.-Y.*; Morita, Yasuji; Akabori, Mitsuo; Minato, Kazuo
Journal of Radioanalytical and Nuclear Chemistry, 296(3), p.1275 - 1286, 2013/06
Times Cited Count：4 Percentile：32.48(Chemistry, Analytical)
Cm was separated and recovered as an oxalate from Cm-
Pu mixed oxide which had been Cm oxide sample prepared 40 years ago. Plutonium ions were removed from the solution prepared by dissolution of Cm-Pu mixed oxide in nitric acid, by using an anion exchange resin column. Curium oxalate, a precursor compound of curium oxide, was prepared from the purified curium solution and supplied for the syntheses and measurements of the thermochemical properties of curium compounds.
Minato, Kazuo
Kaku Nenryo, (48-1), p.27 - 30, 2012/12
Japan Atomic Energy Agency set up Fukushima Project Teams at Nuclear Science Research Institute, Nuclear Fuel Cycle Engineering Laboratories, and Oarai Research and Development Center to conduct research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants on the 1st of April, 2012. Fukushima Project Team at Nuclear Science Research Institute is involved in specific research and development projects concerning the spent fuel pool countermeasures, preparation of fuel debris removal, and radioactive waste treatment and disposal. Among these specific research and development projects the accident development analysis and the assessment of simulated fuel debris characteristics are related to nuclear fuel materials research.
Hasegawa, Mitsuru*; Horii, Hiroyuki*; Nomoto, Kazuhiro*; Imai, Yoshio*; Murai, Takashi*; Minato, Tsuneaki*; Kuno, Kazuo*; Tsuchiya, Katsuhiko; Murakami, Haruyuki; Kizu, Kaname; et al.
Proceedings of 24th International Cryogenic Engineering Conference (ICEC 24) and International Cryogenic Materials Conference 2012 (ICMC 2012) (CD-ROM), p.571 - 574, 2012/05
JT-60U magnet system will be upgraded to the superconducting coils (JT-60SA) in the Broader Approach project. JT-60SA magnet system has 18 Toroidal Field coils, a Central Solenoid with 4 modules and 6 Equilibrium Field (EF) coils. This paper describes the manufacturing procedure of EF4 coil, that is the first manufactured EF coil of JT-60SA. The winding pack of EF4 coil was successfully manufactured within geometrical tolerance requirements.
Minato, Kazuo; Ogawa, Toru
Comprehensive Nuclear Materials, 3, p.215 - 236, 2012/03
TRISO coated particle fuel has been developed for the high temperature gas-cooled reactors, which consists of microspherical fuel kernel and coating layers of pyrolytic carbon and silicon carbide. To improve the high temperature stability, the resistance to the chemical attack by fission products and the retention of fission products of the TRISO coated particle fuels, several types of advanced fuels were proposed and tested. Coated particle fuels for fast reactors were also proposed and tested. In this chaper, fuel designs, fabrications, characterization techniques and fuel performance of these advanced coated particle fuels are systematically described.
Minato, Kazuo; Morita, Yasuji; Tsujimoto, Kazufumi; Koyama, Shinichi; Kurata, Masaki*; Inoue, Tadashi*; Ikeda, Kazumi*
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.341 - 349, 2012/00
In order to provide a quantitative assessment for the maturity of the partitioning and transmutation technology relative to its full-scale deployment, a technology readiness level (TRL) process was used. The definitions of TRL used in this study were based on those used in the Global Nuclear Energy Partnership (GNEP). The TRL was evaluated and the technology pathway was discussed for the systems of FBR and ADS for the minor actinides (MA) transmutation, MA partitioning processes, and MA-bearing fuels. Through the evaluation, it was recognized that hard requirements to be satisfied were present at TRL 5 for each technology development. The introduction of lab-scale tests with actual spent fuel for MA partitioning process and with actual separated materials for MA-bearing fuels fabrication and irradiation before the engineering scale tests may be effective and efficient solution.
Osaka, Masahiko; Konashi, Kenji*; Hayashi, Hirokazu; Li, D.*; Homma, Yoshiya*; Yamamura, Tomoo*; Sato, Isamu; Miwa, Shuhei; Sekimoto, Shun*; Kubota, Takumi*; et al.
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
Summer schools for future experts have successfully been completed under Japan Actinide Network (J-ACTINET) for the purpose of development of human resources who are expected to be engaged in every areas of actinide-research/engineering. The first summer school was held in Ibaraki-area in August 2009, followed by the second one in Kansai-area in August 2010. Two summer schools have focused on actual experiences of actinides in actinide-research fields for university students and young researchers/engineers as an introductory course of actinide-researches. Several quasi actinide-handling experiences at the actinide-research fields have attracted attentions of participants at the first school in Ibaraki-area. The actual experiments using actinides-containing solutions have been carried out at the second school in Kansai-area. Future summer schools will be held every year for the sustainable human resource development in various actinide-research fields.
Minato, Kazuo; Konashi, Kenji*; Yamana, Hajimu*; Yamanaka, Shinsuke*; Nagasaki, Shinya*; Ikeda, Yasuhisa*; Sato, Seichi*; Arita, Yuji*; Idemitsu, Kazuya*; Koyama, Tadafumi*
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
Actinide science research is indispensable to maintain sustainable development of innovative nuclear technology. For actinide science research, special facilities with containment and radiation shields are needed to handle actinide materials. The number of facilities for actinide science research has been decreased, especially in universities, due to the high maintenance cost. J-ACTINET was established in 2008 to promote and facilitate actinide science research and to foster many of young scientists and engineers in actinide science. The research program was carried out, through which young researchers were expected to learn how to make experiments with advanced experimental tools and to broaden their horizons. The summer schools and computational science school were held to provide students and young researchers with the opportunities to come into contact with actinide science research. The overseas dispatch program was also carried out.
solutionsUehara, Akihiro*; Fujii, Toshiyuki*; Matsuura, Haruaki*; Sato, Nobuaki*; Nagai, Takayuki; Minato, Kazuo; Yamana, Hajimu*; Okamoto, Yoshihiro
Proceedings in Radiochemistry, 1(1), p.161 - 165, 2011/09
) and CaClFujii, Toshiyuki*; Okude, Genki*; Uehara, Akihiro*; Sekimoto, Shun*; Hayashi, Hirokazu; Akabori, Mitsuo; Minato, Kazuo; Yamana, Hajimu*
Journal of Radioanalytical and Nuclear Chemistry, 288(1), p.181 - 187, 2011/04
Times Cited Count：6 Percentile：44.28(Chemistry, Analytical)Distribution behavior of Ce(III), Am(III), and Cm(III) between tri-n-butyl phosphate solution and molten calcium nitrate hydrate Ca(NO)
HO or molten calcium chloride hydrate CaClHO was studied radiochemically. In Ca(NO)HO systems, maximum separation factors of Ce and Cm to Am were observed to be 12 (Ce/Am) and 1.7 (Cm/Am). The distribution ratios of these elements increased with the decrease of water activity in the hydrates, and the extractabilities at the water deficient region was less sensitive compared to those at the water abundant region. This trend was similar to the coordination circumstance change observed in electronic absorption spectra of Nd(III) in the hydrates.
