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Journal Articles

Advanced analysis technology for new material and product development

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

Journal Articles

HOTLAB 2017; 54th Annual Meeting on Hot Laboratories and Remote Handling

Minato, Kazuo

Nippon Genshiryoku Gakkai-Shi, 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.

Journal Articles

Present state of partitioning and transmutation of long-lived nuclides, 4; Transmutation system using accelerator driven system and technology maturity of partitioning and transmutation

Tsujimoto, Kazufumi; Arai, Yasuo; Minato, Kazuo

Nippon Genshiryoku Gakkai-Shi, 59(11), p.644 - 648, 2017/11

no abstracts in English

Journal Articles

Present state of partitioning and transmutation of long-lived nuclides, 1; Significance of partitioning and transmutation and partitioning and transmutation systems

Minato, Kazuo; Tsujimoto, Kazufumi; Tanabe, Hiromi*; Fujimura, Koji*

Nippon Genshiryoku Gakkai-Shi, 59(8), p.475 - 479, 2017/08

no abstracts in English

Journal Articles

Nuclear facilities and human resource development

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.

Journal Articles

Electrochemical behavior of americium in NaCl-2CsCl melt

Hayashi, Hirokazu; Akabori, Mitsuo; Minato, Kazuo

Journal of Radioanalytical and Nuclear Chemistry, 303(2), p.1331 - 1334, 2015/02

 Percentile:100(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$$_2$$/Cl$$^-$$, respectively.

Journal Articles

Development of closed nuclear fuel cycles in Japan

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.

Journal Articles

Thermal expansion and self-irradiation damage in curium nitride lattice

Takano, Masahide; Hayashi, Hirokazu; Minato, Kazuo

Journal of Nuclear Materials, 448(1-3), p.66 - 71, 2014/05

 Times Cited Count:1 Percentile:85.45(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 $$Delta$$a/a$$_{0}$$ value was 0.43%, which is greater than those for transuranium dioxides available in literature. The undamaged lattice parameter at 297$$pm$$1 K was determined to be 0.50261$$pm$$0.00006 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 $$times$$ 10$$^{-6}$$ K$$^{-1}$$. 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).

Journal Articles

Synthesis of neptunium trichloride and measurements of its melting temperature

Hayashi, Hirokazu; Takano, Masahide; Kurata, Masaki; Minato, Kazuo

Journal of Nuclear Materials, 440(1-3), p.477 - 479, 2013/09

 Times Cited Count:3 Percentile:62.81(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$$_3$$. Lattice parameters of hexagonal NpCl$$_3$$ were determined from the X-ray diffraction pattern to be a = 0.7421 $$pm$$ 0.0006 nm and c = 0.4268 $$pm$$ 0.0003 nm, which fairly agree with the reported values (a = 0.742 $$pm$$ 0.001 nm and c = 0.4281 $$pm$$ 0.0005 nm). Melting temperature of NpCl$$_3$$ 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$$_3$$ was determined to 1070 $$pm$$ 3 K, which is close to the recommended value 1075$$pm$$30 K, which was derived from the mean value of the melting temperature for UCl$$_3$$(1115K) and that for PuCl$$_3$$ (1041 K).

Journal Articles

Separation and recovery of Cm from Cm-Pu mixed oxide samples containing Am impurity

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:3 Percentile:62.81(Chemistry, Analytical)

$$^{244}$$Cm was separated and recovered as an oxalate from $$^{244}$$Cm-$$^{240}$$Pu mixed oxide which had been $$^{244}$$Cm oxide sample prepared 40 years ago. Plutonium ions were removed from the solution prepared by dissolution of $$^{244}$$Cm-$$^{240}$$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.

Journal Articles

Research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants; Activities at Nuclear Science Research Institute, Japan Atomic Energy Agency

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.

Journal Articles

Manufacturing of JT-60SA equilibrium field coils

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.

Journal Articles

Advanced concepts in TRISO fuel

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.

Journal Articles

Technology readiness levels for partitioning and transmutation of minor actinides in Japan

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.

Journal Articles

Actinide-handling experience for training and education of future expert under J-ACTINET

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.

Journal Articles

J-ACTINET activities of training and education for actinide science research

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.

Journal Articles

EXAFS analysis of uranium(IV) and thorium(IV) complexes in concentrated CaCl$$_{2}$$ solutions

Uehara, 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

Journal Articles

Coordination characteristics of trivalent lanthanides and actinides in molten hydrate salts of Ca(NO$$_3$$)$$_2$$ and CaCl$$_2$$

Fujii, 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:4 Percentile:57.93(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$$_3$$)$$_2cdotmathit{R}$$H$$_2$$O or molten calcium chloride hydrate CaCl$$_2cdotmathit{R}$$H$$_2$$O was studied radiochemically. In Ca(NO$$_3$$)$$_2cdotmathit{R}$$H$$_2$$O 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.

Journal Articles

Maturity of partitioning and transmutation technology; Evaluation and proposal based on technology readiness levels

Minato, Kazuo

Nippon Genshiryoku Gakkai-Shi, 52(12), p.796 - 800, 2010/12

Technology Readiness Levels (TRL) approach was used to provide a quantitative assessment for the maturity of the partitioning and transmutation technology in Japan. The main objective of the present TRL evaluation was not to provide absolute quantitative values of TRL, but to discuss how to conduct the research and development of the partitioning and transmutation technology. The TRL approach was briefly explained and an effective and efficient way to develop the partitioning and transmutation technology was proposed based on the TRL evaluation.

Journal Articles

Current status and future plan of research and development on partitioning and transmutation technology in Japan

Oigawa, Hiroyuki; Minato, Kazuo; Morita, Yasuji; Kimura, Takaumi; Arai, Yasuo; Tsujimoto, Kazufumi; Nishihara, Kenji

Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), p.123 - 132, 2010/11

After the first check and review on the partitioning and transmutation (PT) technology by the Japan Atomic Energy Commission (JAEC) in 2000, significant progress was made in respective research areas of the partitioning, fuel fabrication, transmutation and fuel recycling in Japan. The second check and review on the PT technology was made by the JAEC in 2008-2009. The final report issued in April, 2009, mentions that the significance of the PT technology is in three points: reduction of the potential hazard, mitigation of the requirement for geological repository site, and enhancement of the options in the design of the whole system of waste disposal. The current technology levels of the PT for both FBR and ADS were evaluated. The PT technology in general is still in the basic research because of the lack of experimental data for minor actinides (MA). It was, therefore, strongly recommended to accumulate the experimental data for MA as a common basis for both FBR and ADS.

250 (Records 1-20 displayed on this page)