Shun Hirooka

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101002001042870
researchmap Member ID: R000017698

Research Areas

Nanotechnology/Materials / Inorganic materials /

Research History

Apr, 2010 - Present

Japan Atomic Energy Agency
Mar, 2014 - Mar, 2015

MST-8

Papers

Influence of Oxygen to Metal ratio on properties of UO2-cladding simulated debris

Hirooka Shun, Kato Masato, Morimoto Kyoichi, Komeno Akira, Uchida Teppei, Akashi Masatoshi

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012 372-372, 2012
Melting temperature and thermal conductivities of corium prepared from UO$_{2}$ and zircalloy-2

Kato Masato, Uchida Teppei, Hirooka Shun, Akashi Masatoshi, Komeno Akira, Morimoto Kyoichi

Materials Research Society Symposium Proceedings, Vol.1444, 1444 91-96, Sep, 2012 Peer-reviewed
Thermal expansion of corium prepared from UO$_2$ and zircalloy-2

Hirooka Shun, Akashi Masatoshi, Uchida Teppei, Morimoto Kyoichi, Kato Masato

Materials Research Society Symposium Proceedings, Vol.1444, 97-101, Sep, 2012 Peer-reviewed
Oxygen potentials of PuO$_{2-x}$

Komeno Akira, Kato Masato, Hirooka Shun, Sunaoshi Takeo*

Materials Research Society Symposium Proceedings, Vol.1444, 1444 85-89, Sep, 2012 Peer-reviewed
Effect of oxygen-to-metal ratio on properties of corium prepared from UO$_{2}$ and zircaloy-2

Hirooka Shun, Kato Masato, Morimoto Kyoichi, Komeno Akira, Uchida Teppei, Akashi Masatoshi

Journal of Nuclear Materials, 437(1-3) 130-134, Jun, 2013 Peer-reviewed
Development and verification of the thermal behavior analysis code for MA containing MOX fuels

Ikusawa Yoshihisa, Ozawa Takayuki, Hirooka Shun, Maeda Koji, Kato Masato, Maeda Seiichiro

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 6, Jul, 2014 Peer-reviewed
Two-Step Sintering of Non-Stoichiometric CeO_2-x

Hitoshi Abe, Makoto Nanko, Masato Kato, Shun Hirooka

Materials Science Forum, 804 7-10, Oct, 2014
The Influences of Pu and Zr on the melting temperatures of the UO$_{2}$-PuO$_{2}$-ZrO$_{2}$ pseudo-ternary system

Morimoto Kyoichi, Hirooka Shun, Akashi Masatoshi, Watanabe Masashi, Sugata Hiromasa*

Journal of Nuclear Science and Technology, 52(10) 1247-1252, Oct, 2015 Peer-reviewed
Sintering behavior of (U,Ce)O$_{2}$ and (U,Pu)O$_{2}$

Nakamichi Shinya, Hirooka Shun, Sunaoshi Takeo*, Kato Masato, Nelson A.*, McClellan K.*

Transactions of the American Nuclear Society, 113(1) 617-618, Oct, 2015 Peer-reviewed
Thermodynamic assessment of the oxygen rich U–Ce–O system

J.W. McMurray, S. Hirooka, T. Murakami, K. Suzuki, J.T. White, S.L. Voit, A.T. Nelson, B.W. Slone, T.M. Besmann, K.J. McClellan …

Journal of Nuclear Materials, 467 588-600, Dec, 2015
Oxygen potentials, oxygen diffusion coefficients and defect equilibria of nonstoichiometric (U,Pu)O$_{2\pm x}$

Kato Masato, Watanabe Masashi, Matsumoto Taku, Hirooka Shun, Akashi Masatoshi

Journal of Nuclear Materials, 487 424-432, Apr, 2017 Peer-reviewed
Sound speeds in and mechanical properties of (U,Pu)O$_{2-x}$

Hirooka Shun, Kato Masato

Journal of Nuclear Science and Technology, 55(3) 356-362, Mar, 2018 Peer-reviewed
Modeling and simulation of redistribution of oxygen-to-metal ratio in MOX

Hirooka Shun, Kato Masato, Watanabe Masashi

Transactions of the American Nuclear Society, 118 1624-1626, Jun, 2018 Peer-reviewed
Physical properties of non-stoichiometric (U,Pu)O$_{2}$

Watanabe Masashi, Matsumoto Taku, Hirooka Shun, Morimoto Kyoichi, Kato Masato

2018 GIF Symposium Proceedings (Internet), 315-320, May, 2020 Peer-reviewed
Oxygen potential and self-irradiation effects on fuel temperature in Am-MOX

Ikusawa Yoshihisa, Hirooka Shun, Uno Masayoshi*

2018 GIF Symposium Proceedings (Internet), 321-327, May, 2020 Peer-reviewed
Effect of O/M ratio on sintering behavior of (Pu$_{0.3}$U$_{0.7}$)O$_{2-x}$

Nakamichi Shinya, Hirooka Shun, Kato Masato, Sunaoshi Takeo*, Nelson A. T.*, McClellan K. J.*

Journal of Nuclear Materials, 535 152188\_1-152188\_8, Jul, 2020 Peer-reviewed
Oxygen potential measurement of (U,Pu,Am)O$_{2 \pm x}$ and (U,Pu,Am,Np)O$_{2 \pm x}$

Hirooka Shun, Matsumoto Taku, Kato Masato, Sunaoshi Takeo*, Uno Hiroki*, Yamada Tadahisa*

Journal of Nuclear Materials, 542 152424\_1-152424\_9, Dec, 2020 Peer-reviewed
Development of fuel performance analysis code, BISON for MOX, named Okami; Analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring

Ozawa Takayuki, Hirooka Shun, Kato Masato, Novascone S.*, Medvedev P.*

Journal of Nuclear Materials, 553 153038\_1-153038\_16, Sep, 2021 Peer-reviewed
Relative oxygen potential measurements of (U,Pu)O$_{2}$ with Pu = 0.45 and 0.68 and related defect formation energy

Hirooka Shun, Matsumoto Taku, Sunaoshi Takeo*, Hino Tetsushi*

Journal of Nuclear Materials, 558 153375\_1-153375\_8, Jan, 2022 Peer-reviewed
Recent studies on fuel properties and irradiation behaviors of Am/Np-bearing MOX

Hirooka Shun, Yokoyama Keisuke, Kato Masato

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 8, Apr, 2022 Peer-reviewed

Misc.

Materials science and fuel technologies of uranium and plutonium mixed oxide

Kato Masato, Machida Masahiko, Hirooka Shun, Nakamichi Shinya, Ikusawa Yoshihisa, Nakamura Hiroki, Kobayashi Keita, Ozawa Takayuki, Maeda Koji, Sasaki Shinji …

Materials Science and Fuel Technologies of Uranium and Plutonium mixed Oxide, 171, Oct, 2022
Mechanical and thermal properties of (U,Pu)O$_{2-x}$

Hirooka Shun, Kato Masato

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 6, Jun, 2017
Oxygen thermochemistry of urania-rare earth system; UO$_2$-CeO$_2$

Hirooka Shun, Murakami Tatsutoshi, Nelson A. T.*, McClellan K. J.*

INL/EXT-14-33515, 34-36, Oct, 2014
Property measurements and inner state estimation of simulated fuel debris

Hirooka Shun, Kato Masato, Morimoto Kyoichi, Washiya Tadahiro

Proceedings of 19th Pacific Basin Nuclear Conference (PBNC 2014) (USB Flash Drive), 8, Aug, 2014
Development of science-based fuel technologies for Japan's Sodium-Cooled Fast Reactors

Kato Masato, Hirooka 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, Aug, 2014
Melting temperatures of the ZrO$_{2}$-MOX system

Uchida Teppei, Hirooka Shun, Sugata Hiromasa*, Shibata Katsuya*, Sato Daisuke*, Kato Masato, Morimoto Kyoichi

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), 1549-1553, Sep, 2013
Oxidation and reduction behaviors of plutonium and uranium mixed oxide powders

Hirooka Shun, Kato Masato, Tamura Tetsuya*, Nelson A. T.*, McClellan K. J.*, Suzuki Kiichi

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 8, Mar, 2013
Oxide fuel fabrication technology development of the FaCT project, 3; Analysis of sintering behavior for MOX pellet production

Hirooka Shun, Kato Masato, Takeuchi Kentaro, Takano Tatsuo

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6, Dec, 2011

Presentations

Evaluation of burn-up effect on MOX fuel thermal conductivity, 2; Investigation of thermal conductivity model considering burn-up

Hirooka Shun, Horii Yuta, Murakami Tatsutoshi

日本原子力学会2024年春の年会
Machine learning sintering density prediction model for MOX fuel pellet

Nakajima Tatsuya, Kato Masato, Tsuchimochi Ryota, Hirooka Shun, Watanabe Masashi, Nakamichi Shinya, Murakami Tatsutoshi, Ishii Katsunori

日本原子力学会2024年春の年会
Evaluation of burn-up effect on MOX fuel thermal conductivity, 1; Thermal conductivity evaluation of simulated FP-doped MOX

Horii Yuta, Hirooka Shun, Vauchy R., Uno Hiroki*, Ogasawara Masahiro*, Yamada Tadahisa*, Murakami Tatsutoshi

日本原子力学会2024年春の年会
High temperature physical properties and defect chemistry of fluorite-type compounds

Kato Masato, Nakamura Hiroki, Watanabe Masashi, Hirooka Shun, Machida Masahiko

日本原子力学会2024年春の年会
Study on stable storage of nuclear fuel materials, 1; Synthesis of zirconolite with U-Ce mixed oxide

Hayashizaki Kohei, Hirooka Shun, Akiyama Daisuke*, Kirishima Akira*, Murakami Tatsutoshi

日本原子力学会2024年春の年会
Phase separation and recombinaison in U1-yPuyO$_{2}$-x with y = 0.30, 0.45, and 1.00

Vauchy R., Ogasawara Masahiro*, Yamada Tadahisa*, Sunaoshi Takeo*, Tamura Tetsuya*, Horii Yuta, Hirooka Shun, Kato Masato, Murakami Tatsutoshi

日本原子力学会2024年春の年会
Manufacturing and property measurements of homogeneous simulated FP (Nd/Sm/Gd/Zr)-doped MOX

Horii Yuta, Hirooka Shun, Vauchy R., Hayashizaki Kohei, Uno Hiroki*, Tamura Tetsuya*, Sunaoshi Takeo*, Ohwada Hideaki*, Yamada Tadahisa*, Murakami Tatsutoshi

Materials in Nuclear Energy Systems (MiNES 2023)
Measurement of high temperature heat capacity and thermal diffusivity of (U,Pu)O$_{2}$ as a function of Pu content

Hirooka Shun, Matsumoto Taku, Morimoto Kyoichi, Ogasawara Masahiro*, Murakami Tatsutoshi, Kato Masato

Materials in Nuclear Energy Systems (MiNES 2023)
Ionic radii in fluorite structured actinide dioxides

Vauchy R., Hirooka Shun, Murakami Tatsutoshi

Materials in Nuclear Energy Systems (MiNES 2023)
Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels, 15; Summary and future plans

Hirooka Shun, Kato Masato, Uno Masayoshi*, Arima Tatsumi*

日本原子力学会2023年秋の大会
New developments in nuclear fuel research through integration with data science, 4; Development of machine-learning gap conductance model

Kato Masato, Uwaba Tomoyuki, Watanabe Masashi, Hirooka Shun, Konashi Kenji*, Kurosaki Ken*

日本原子力学会2023年秋の大会
Manufacturing of homogeneous simulated FPs (Nd$_{2}$O$_{3}$/Sm$_{2}$O$_{3}$/Gd$_{2}$O$_{3}$/ZrO$_{2}$)-doped MOX for studies on MOX fuel properties

Horii Yuta, Hirooka Shun, Vauchy R., Hayashizaki Kohei, Uno Hiroki*, Tamura Tetsuya*, Sunaoshi Takeo*, Ohwada Hideaki*, Yamada Tadahisa*, Murakami Tatsutoshi

日本原子力学会2023年秋の大会
Thermal conductivity measurement of homogenenous/heterogeneous simulated FP-doped MOX

Horii Yuta, Hirooka Shun, Uno Hiroki*, Ogasawara Masahiro*, Yamada Tadahisa*, Furusawa Naoya*, Murakami Tatsutoshi

日本原子力学会核燃料部会第33回「核燃料・夏期セミナー」
Sintering of MOX powder with different particle size distribution prepared by dry-recycling process

Hayashizaki Kohei, Hirooka Shun, Sunaoshi Takeo*, Uno Hiroki*, Nakamichi Shinya, Murakami Tatsutoshi

30th International Conference on Nuclear Engineering (ICONE30)
Challenges in nuclear material storage in Japanese MOX fuel fabrication facilities

Hirooka Shun, Tsuchimochi Ryota, Matsumoto Taku, Nakamichi Shinya, Murakami Tatsutoshi

30th International Conference on Nuclear Engineering (ICONE30)
Sintering behavior of dry-recycled MOX powder with various particle size distribution

Hayashizaki Kohei, Hirooka Shun, Sunaoshi Takeo*, Nakamichi Shinya, Murakami Tatsutoshi

日本原子力学会2023年春の年会
Oxygen potential measurements of Nd doped (U,Pu,Am)O$_{2}$ mixed oxides

Vauchy R., Hirooka Shun, Sunaoshi Takeo*, Nakamichi Shinya, Murakami Tatsutoshi, Kato Masato

日本原子力学会2023年春の年会
Development of visual inspection technology of pellets using machine learning, 2; Demonstration experiment using MOX pellets and consideration for introduction to production lines

Goto Kenta, Hirooka Shun, Horii Yuta, Nakamichi Shinya, Murakami Tatsutoshi, Shibanuma Kimikazu, Ono Takanori, Yamamoto Kazuya, Hatanaka Nobuhiro, Okumura Kazuyuki

日本原子力学会2023年春の年会
Enthalpy measurement and evaluation of specific heat on MOX at high temperature

Hirooka Shun, Matsumoto Taku, Ogasawara Masahiro*, Kato Masato

日本原子力学会2023年春の年会
Machine learning sintering density prediction model for MOX fuel pellet

Tsuchimochi Ryota, Kato Masato, Nakajima Tatsuya, Hirooka Shun, Watanabe Masashi, Nakamichi Shinya, Murakami Tatsutoshi, Ishii Katsunori

日本原子力学会2023年春の年会

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