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2
3 and their derivativesKakihana, Masashi*; Takeuchi, Tetsuya*; Haga, Yoshinori; Harima, Hisatomo*; Hedo, Masato*; Nakama, Takao*; Onuki, Yoshichika*
Kotai Butsuri, 55(10), p.505 - 514, 2020/10
no abstracts in English
and EuAu with the characteristic hexagonal structureMatsuda, Shinya*; Ota, Joji*; Nakaima, Kenri*; Iha, Wataru*; Gochi, Jun*; Uwatoko, Yoshiya*; Nakashima, Miho*; Amako, Yasushi*; Honda, Fuminori*; Aoki, Dai*; et al.
Philosophical Magazine, 100(10), p.1244 - 1257, 2020/04
Times Cited Count：2 Percentile：45.37(Materials Science, Multidisciplinary)
Si single crystal grown by the flux methodTakeuchi, Tetsuya*; Haga, Yoshinori; Taniguchi, Toshifumi*; Iha, Wataru*; Ashitomi, Yosuke*; Yara, Tomoyuki*; Kida, Takanori*; Tahara, Taimu*; Hagiwara, Masayuki*; Nakashima, Miho*; et al.
Journal of the Physical Society of Japan, 89(3), p.034705_1 - 034705_15, 2020/03
Times Cited Count：0 Percentile：0(Physics, Multidisciplinary)Onuki, Yoshichika*; Kakihana, Masashi*; Iha, Wataru*; Nakaima, Kenri*; Aoki, Dai*; Nakamura, Ai*; Honda, Fuminori*; Nakashima, Miho*; Amako, Yasushi*; Gochi, Jun*; et al.
JPS Conference Proceedings (Internet), 29, p.012001_1 - 012001_9, 2020/02
Iha, Wataru*; Kakihana, Masashi*; Matsuda, Shinya*; Honda, Fuminori*; Haga, Yoshinori; Takeuchi, Tetsuya*; Nakashima, Miho*; Amako, Yasushi*; Gochi, Jun*; Uwatoko, Yoshiya*; et al.
Journal of Alloys and Compounds, 788, p.361 - 366, 2019/06
Times Cited Count：2 Percentile：25.87(Chemistry, Physical)Kono, Takahiko; Tanaka, Masato*; Sakoda, Akihiro; Tanaka, Hitomi*; Takeuchi, Masato*; Kataoka, Noriaki*
Proceedings of World Engineers Convention Australia 2019 (WEC 2019) (Internet), p.486 - 496, 2019/00
SiTakeuchi, Tetsuya*; Yara, Tomoyuki*; Ashitomi, Yosuke*; Iha, Wataru*; Kakihana, Masashi*; Nakashima, Miho*; Amako, Yasushi*; Honda, Fuminori*; Homma, Yoshiya*; Aoki, Dai*; et al.
Journal of the Physical Society of Japan, 87(7), p.074709_1 - 074709_14, 2018/07
Times Cited Count：7 Percentile：63.33(Physics, Multidisciplinary)(Ge
Si
) based on the doniach phase diagramIha, Wataru*; Yara, Tomoyuki*; Ashitomi, Yosuke*; Kakihana, Masashi*; Takeuchi, Tetsuya*; Honda, Fuminori*; Nakamura, Ai*; Aoki, Dai*; Gochi, Jun*; Uwatoko, Yoshiya*; et al.
Journal of the Physical Society of Japan, 87(6), p.064706_1 - 064706_14, 2018/06
Times Cited Count：15 Percentile：78.13(Physics, Multidisciplinary)Ikawa, Nozomu*; Mukai, Yoichi*; Nishida, Akemi; Hamamoto, Takuji*; Kano, Toshiya*; Ota, Toshiro*; Nakamura, Naohiro*; Komuro, Masato*; Takeuchi, Masato*
Proceedings of 12th International Conference on Shock and Impact Loads on Structures (SI 2017) (USB Flash Drive), p.259 - 268, 2017/06
Accidental actions on building structures involve impact and explosion loads. The design loads due to impact are determined by experiment data, impact simulation and energetics approach. These loads are presented in the form of load-time (F-t) curves caused by collision and explosion. It is assumed that the structure is rigid and immovable and that impacting body absorbs all the energy (i.e., hard impact condition is supposed), because this assumption gives conservative results in general. Responses of individual structural members directly-subjected to an impulsive load are evaluated. These responses are classified into three types; impulsive response, dynamic response, and quasi-static response. The maximum responses are basically estimated by direct integration method with a single-degree-of-freedom (SDOF) model. The procedure of the SDOF modelling based on the classification of types of members and failure modes is proposed in AIJ guideline.
Kawasaki, Masatsugu; Nakajima, Junya; Yoshida, Keisuke; Kato, Saori; Nishino, Sho; Nozaki, Teo; Nakagawa, Masahiro; Tsunoda, Junichi; Sugaya, Yuki; Hasegawa, Rie; et al.
JAEA-Data/Code 2017-004, 57 Pages, 2017/03
JAEA-Data-Code-2017-004.pdf:2.34MB
In emergency situation of nuclear facilities, we need to estimate the radiation dose due to radiation and radioactivity to grasp the influence range of the accident in the early stage. Therefore, we prepare the case studies of dose assessment for public exposure dose and personal exposure dose and contribute them to emergency procedures. This document covers about accidents of nuclear facilities in Nuclear Science Research Institute and past accident of nuclear power plant, and it can be used for inheritance of techniques of emergency dose assessment.
CoTeruya, Atsushi*; Kakihana, Masashi*; Takeuchi, Tetsuya*; Aoki, Dai*; Honda, Fuminori*; Nakamura, Ai*; Haga, Yoshinori; Matsubayashi, Kazuyuki*; Uwatoko, Yoshiya*; Harima, Hisatomo*; et al.
Journal of the Physical Society of Japan, 85(3), p.034706_1 - 034706_10, 2016/03
Times Cited Count：1 Percentile：13.94(Physics, Multidisciplinary)Kakihana, Masashi*; Teruya, Atsushi*; Nishimura, Kengo*; Nakamura, Ai*; Takeuchi, Tetsuya*; Haga, Yoshinori; Harima, Hisatomo*; Hedo, Masato*; Nakama, Takao*; Onuki, Yoshichika
Journal of the Physical Society of Japan, 84(9), p.094711_1 - 094711_8, 2015/09
Times Cited Count：13 Percentile：70.14(Physics, Multidisciplinary)Nishida, Akemi; Ohashi, Yasuhiro*; Obi, Hirotoshi*; Takeuchi, Yoshitaka*; Kano, Toshiya*; Ryuzaki, Hibiki*; Ota, Toshiro*; Kishi, Tokumitsu*; Komuro, Masato*; Nakamura, Naohiro*
Kenchikubutsu No Taishogeki Sekkei No Kangaekata, p.161 - 202, 2015/01
Though design guidelines for earthquake and wind loads are specified for buildings, the guideline for impulsive load as explosion and impact is not specified yet in architectural field. This document corresponds to Chapter 8 of the book titled "Introduction to Shock-Resistant Design of Buildings" which made towards the impact design guideline. Some design examples are presented to illustrate the applicability of the tentative guideline for impulsive loads. Two buildings - a steel frame and a reinforced concrete frame building structures - located at the corner of a crossroads are selected. Dynamic responses and the corresponding damage states are illustrated for the cases of two buildings subjected to impact loads due to road vehicle crashes, internal and external explosions. The idea has been shown in this document are those that can be applied to nuclear facilities.
Kato, Masato; Hiroka, Shun; Ikusawa, Yoshihisa; Takeuchi, Kentaro; Akashi, Masatoshi; Maeda, Koji; Watanabe, Masashi; Komeno, Akira; Morimoto, Kyoichi
Proceedings of 19th Pacific Basin Nuclear Conference (PBNC 2014) (USB Flash Drive), 12 Pages, 2014/08
Uranium and plutonium mixed oxide (MOX) fuel has been developed for Japan sodium-cooled fast reactors. Science based fuel technologies have been developed to analyse behaviours of MOX pellets in the sintering process and irradiation conditions. The technologies can provide appropriate sintering conditions, irradiation behaviour analysis results and so on using mechanistic models which are derived based on theoretical equations to represent various properties.
and EuAlNakamura, Ai*; Hiranaka, Yuichi*; Hedo, Masato*; Nakama, Takao*; Miura, Yasunao*; Tsutsumi, Hiroki*; Mori, Akinobu*; Ishida, Kazuhiro*; Mitamura, Katsuya*; Hirose, Yusuke*; et al.
JPS Conference Proceedings (Internet), 3, p.011012_1 - 011012_6, 2014/06
Nakamura, Ai*; Hiranaka, Yuichi*; Hedo, Masato*; Nakama, Takao*; Tatetsu, Yasutomi*; Maehira, Takahiro*; Miura, Yasunao*; Mori, Akinobu*; Tsutsumi, Hiroki*; Hirose, Yusuke*; et al.
Journal of the Physical Society of Japan, 82(12), p.124708_1 - 124708_6, 2013/12
Times Cited Count：18 Percentile：72.91(Physics, Multidisciplinary)Nakamura, Ai*; Hiranaka, Yuichi*; Hedo, Masato*; Nakama, Takao*; Miura, Yasunao*; Tsutsumi, Hiroki*; Mori, Akinobu*; Ishida, Kazuhiro*; Mitamura, Katsuya*; Hirose, Yusuke*; et al.
Journal of the Physical Society of Japan, 82(10), p.104703_1 - 104703_10, 2013/10
Times Cited Count：29 Percentile：82(Physics, Multidisciplinary)
Pu
)O
at 1773 and 1873 K, and its analysis based on point defect chemistryKato, Masato; Nakamichi, Shinya; Takeuchi, Kentaro; Sunaoshi, Takeo*
CALPHAD; Computer Coupling of Phase Diagrams and Thermochemistry, 35(4), p.623 - 626, 2011/12
Times Cited Count：8 Percentile：48.58(Thermodynamics)Uranium and plutonium mixed oxide (MOX) has been used as fuels of fast reactors. The MOX having fluorite structure is an oxygen nonstoichiometric compound which is stable in hyper- and hypo-stoichiometric composition range. The stoichiometry of MOX significantly affects their properties. So, it is essential to know the relation between stoichiometry and oxygen potential to develop MOX fuels. In this work, the oxygen potentials of (UPu)O were measured at high temperatures of 1773, and 1873K. The measurements were carried out by gas equilibrium method using thermo-gravimetry. Th The oxygen partial pressure was adjusted by controlling the ratio of H
/HO in the flowing gas atmosphere, and the oxygen potential was determined. The oxygen potentials were determined as functions of O/M ratio, and temperature. The data at stoichiometric composition were estimated to be -311kJ/mol and -299kJ/mol at 1773K, and 1873K based on point defect model.
Sudo, Katsuo; Takano, Tatsuo; Takeuchi, Kentaro; Kihara, Yoshiyuki; Kato, Masato
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
Japan Atomic Energy Agency has been contracted to advance the Fast Reactor Cycle Technology Development project. As one part of the project, a simplified MOX pellet fabrication method has been developed for fast reactor fuels. In previous reports, feasibility of a simplified MOX pellet fabrication method was confirmed through hot and cold laboratory-scale experiments. The die wall lubrication pressing technology was one of the important technologies included in the development of the simplified MOX pellet fabrication method. In the work described here, a pressing machine with a die wall lubrication system was developed, and MOX pellet fabrication experiments were carried out on the kilogram MOX scale.
Takano, Tatsuo; Sudo, Katsuo; Takeuchi, Kentaro; Kihara, Yoshiyuki; Kato, Masato
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 7 Pages, 2011/12
Development of high burn-up fuels is essential to improve economy of the fast reactor fuel cycle. Increase of fuel burn-up is known to cause fuel-cladding chemical interaction (FCCI) and it mainly determines a lifetime of fuel pin. In order to extend a lifetime of fuel pin by mitigating FCCI, development of low oxygen-to-metal (O/M) MOX fuel has been carried out in plutonium fuel development center of JAEA. MOX fuel needs adjustment of the O/M ratio to less than 1.97 for high burn-up of 150 GWd/t. Therefore, O/M adjustment technology is one of the main subjects in development of a simplified MOX pellet fabrication method which has been advanced in the FaCT (Fast reactor Cycle Technology development) project. In previous work, changes in O/M ratio of MOX pellet during heat treatment were calculated from measurement results of oxygen potentials. On the basis of above calculation, heating tests were carried out to prepare low O/M ratio MOX pellets on a laboratory scale. The O/M ratios obtained in the heating tests were well consistent with calculation results. In the present study, a kilogram MOX scale furnace to adjust O/M ratio of MOX pellets for targeted value has been developed as next step.
