Jun Aihara - My portal

Profile Information

J-GLOBAL ID: 202101000489766403
researchmap Member ID: R000017530

Research Areas

Nanotechnology/Materials / Structural and functional materials /

Papers

Influences of the ZrC coating process and heat treatment on ZrC-coated kernels used as fuel in Pu-burner high temperature gas-cooled reactor in Japan

Aihara Jun, Ueta Shohei, Honda Masaki*, Mizuta Naoki, Goto Minoru, Tachibana Yukio, Okamoto Koji*

Journal of Nuclear Science and Technology, 58(1) 107-116, Jan, 2021 Peer-reviewed
Development of fabrication and inspection technologies for oxidation-resistant fuel element for high-temperature gas-cooled reactors

Aihara Jun, Yasuda Atsushi*, Ueta Shohei, Ogawa Hiroaki, Honda Masaki*, Ohira Koichi*, Tachibana Yukio

Nippon Genshiryoku Gakkai Wabun Rombunshi, 18(4) 237-245, Dec, 2019 Peer-reviewed
Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan

Aihara Jun, Ueta Shohei, Honda Masaki*, Mizuta Naoki, Goto Minoru, Tachibana Yukio, Okamoto Koji*

Journal of Nuclear Materials, 522 32-40, Aug, 2019 Peer-reviewed
Development of fabrication technology for oxidation-resistant fuel elements for high-temperature gas-cooled reactors

Aihara Jun, Honda Masaki*, Ueta Shohei, Ogawa Hiroaki, Ohira Koichi*, Tachibana Yukio

Nippon Genshiryoku Gakkai Wabun Rombunshi, 18(1) 29-36, Mar, 2019 Peer-reviewed
Investigation of irradiated properties of extended burnup TRISO fuel

Shaimerdenov A.*, Gizatulin S.*, Kenzhin Y.*, Dyussambayev D.*, Ueta Shohei, Aihara Jun, Shibata Taiju

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 6, Oct, 2018 Peer-reviewed
Study on Pu-burner high temperature gas-cooled reactor in Japan; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Mizuta Naoki, Goto Minoru, Fukaya Yuji, Tachibana Yukio, Okamoto Koji*

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7, Oct, 2018 Peer-reviewed
Study on Pu-burner high temperature gas-cooled reactor in Japan; Design study of fuel and reactor core

Goto Minoru, Aihara Jun, Inaba Yoshitomo, Ueta Shohei, Fukaya Yuji, Okamoto Koji*

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 6, Oct, 2018 Peer-reviewed
Development of security and safety fuel for Pu-burner HTGR; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Goto Minoru, Tachibana Yukio, Okamoto Koji*

Mechanical Engineering Journal (Internet), 5(5) 18-00084\_1-18-00084\_9, Oct, 2018 Peer-reviewed
Development of security and safety fuel for Pu-burner HTGR, 5; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Goto Minoru, Tachibana Yukio, Okamoto Koji*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 4, Jul, 2017 Peer-reviewed
Development of security and safety fuel for Pu-burner HTGR, 2; Design study of fuel and reactor core

Goto Minoru, Ueta Shohei, Aihara Jun, Inaba Yoshitomo, Fukaya Yuji, Tachibana Yukio, Okamoto Koji*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 6, Jul, 2017 Peer-reviewed
Irradiation test and post irradiation examination of the high burnup HTGR fuel

Ueta Shohei, Aihara Jun, Shaimerdenov A.*, Dyussambayev D.*, Gizatulin S.*, Chakrov P.*, Sakaba Nariaki

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), 246-252, Nov, 2016 Peer-reviewed
Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts

Aihara Jun, Goto Minoru, Inaba Yoshitomo, Ueta Shohei, Sumita Junya, Tachibana Yukio

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), 814-822, Nov, 2016 Peer-reviewed
Conceptual study of a plutonium burner high temperature gas-cooled reactor with high nuclear proliferation resistance

Goto Minoru, Demachi Kazuyuki*, Ueta Shohei, Nakano Masaaki*, Honda Masaki*, Tachibana Yukio, Inaba Yoshitomo, Aihara Jun, Fukaya Yuji, Tsuji Nobumasa* …

Proceedings of 21st International Conference \& Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), 507-513, Sep, 2015 Peer-reviewed
Fuel performance under continuous high-temperature operation of the HTTR

Ueta Shohei, Aihara Jun, Sakaba Nariaki, Honda Masaki*, Furihata Noboru*, Sawa Kazuhiro

Journal of Nuclear Science and Technology, 51(11-12) 1345-1354, Nov, 2014 Peer-reviewed
Development plan of high burnup fuel for high temperature gas-cooled reactors in future

Aihara Jun, Ueta Shohei, Honda Masaki*, Blynskiy P.*, Gizatulin S.*, Sakaba Nariaki, Tachibana Yukio

Journal of Nuclear Science and Technology, 51(11-12) 1355-1363, Nov, 2014 Peer-reviewed
R\&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Ueta Shohei, Sumita Junya, Shibata Taiju, Aihara Jun, Fujita Ichiro*, Ohashi Jun*, Nagaishi Yoshihide*, Muto Takenori*, Sawa Kazuhiro, Sakaba Nariaki

Nuclear Engineering and Design, 271 309-313, May, 2014 Peer-reviewed
A Small-sized HTGR system design for multiple heat applications for developing countries

Ohashi Hirofumi, Sato Hiroyuki, Goto Minoru, Yan X., Sumita Junya, Tazawa Yujiro*, Nomoto Yasunobu, Aihara Jun, Inaba Yoshitomo, Fukaya Yuji …

International Journal of Nuclear Energy, 2013 918567\_1-918567\_18, Jan, 2013 Peer-reviewed
Post-irradiation SEM study of ZrC-based TRISO coatings from the PYCASSO experiments

Hania R.*, M\'enard G.*, Aihara Jun, Ueta Shohei, Knol S.*, De Jong A.*, Van den Berg F.*, Van Staveren T.*, De Groot S.*

Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 5, Oct, 2012 Peer-reviewed
R\&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR

Ueta Shohei, Sumita Junya, Shibata Taiju, Aihara Jun, Fujita Ichiro*, Ohashi Jun*, Nagaishi Yoshihide*, Muto Takenori*, Sawa Kazuhiro, Sakaba Nariaki

Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology (HTR 2012) (USB Flash Drive), 6, Oct, 2012 Peer-reviewed
Suggested failure probability calculation method for Japanese high-quality high-temperature gas-cooled reactor (HTGR) fuel

Aihara Jun, Ueta Shohei, Shibata Taiju, Sawa Kazuhiro

Nippon Genshiryoku Gakkai Wabun Rombunshi, 11(2) 158-163, Jun, 2012 Peer-reviewed

Misc.

Code-B-2.5.2 for stress calculation for SiC-TRISO fuel particle

Aihara Jun, Goto Minoru, Ueta Shohei, Tachibana Yukio

JAEA-Data/Code 2019-018, 22, Jan, 2020
Comparison between HTFP code and minory changed FORNAX-A code

Aihara Jun, Ueta Shohei, Goto Minoru, Inaba Yoshitomo, Shibata Taiju, Ohashi Hirofumi

JAEA-Technology 2018-002, 70, Jun, 2018
Confirmation of feasibility of fabrication technology and characterization of high-packing fraction fuel compact for HTGR

Mizuta Naoki, Ueta Shohei, Aihara Jun, Shibata Taiju

JAEA-Technology 2017-004, 22, Mar, 2017
Application of FORNAX-A

Aihara Jun, Ueta Shohei, Nishihara Tetsuo

JAEA-Technology 2015-040, 32, Feb, 2016
HTFP for calculation of amount of additionally released fission products from fuel rods of pin-in-block-type high temperature gas-cooled reactors during accident

Nomoto Yasunobu, Aihara Jun, Nakagawa Shigeaki, Isaka Kazuyoshi, Ohashi Hirofumi

JAEA-Data/Code 2015-008, 39, Jun, 2015
Preliminary evaluation of integrity of coated fuel particles under normal operation in core of small-sized HTGR system HTR50S at 1st. step of Phase I

Aihara Jun, Goto Minoru, Inaba Yoshitomo, Isaka Kazuyoshi, Ohashi Hirofumi, Tachibana Yukio

JAEA-Technology 2014-009, 29, May, 2014
FORNAX-A for calculation of fission product release amount from fuel rods of pin-in-block-type high temperature gas-cooled reactors

Aihara Jun, Ueta Shohei, Nakagawa Shigeaki, Sawa Kazuhiro, Ohashi Hirofumi, Tachibana Yukio

JAEA-Data/Code 2013-025, 64, Mar, 2014
Conceptual design of small-sized HTGR system, 5; Safety design and preliminary safety analysis

Ohashi Hirofumi, Sato Hiroyuki, Tazawa Yujiro, Aihara Jun, Nomoto Yasunobu, Imai Yoshiyuki, Goto Minoru, Isaka Kazuyoshi, Tachibana Yukio, Kunitomi Kazuhiko

JAEA-Technology 2013-017, 71, Feb, 2014
Code-B-2 for stress calculation for SiC-TRISO fuel particle

Aihara Jun, Ohashi Hirofumi, Sawa Kazuhiro, Tachibana Yukio

JAEA-Data/Code 2012-030, 13, Feb, 2013
Microstructures observations and positron annihilation spectroscopic measurements of ZrC layers fabricated by Japan Atomic Energy Agency in recent R\&D

Aihara Jun, Ueta Shohei, Maekawa Masaki, Kawasuso Atsuo, Sawa Kazuhiro

JAEA-Review 2012-047, 34, Feb, 2013
Evaluation of integrity of coated fuel particles of practical high temperature gas-cooled reactor system

Aihara Jun, Ueta Shohei, Ohashi Hirofumi, Tachibana Yukio

JAEA-Technology 2012-044, 9, Feb, 2013
Code-B-1 for stress/strain calculation for TRISO fuel particle (Contract research)

Aihara Jun, Ueta Shohei, Shibata Taiju, Sawa Kazuhiro

JAEA-Data/Code 2011-016, 10, Dec, 2011
Test plan using the HTTR for commercialization of GTHTR300C

Tachibana Yukio, Nishihara Tetsuo, Sakaba Nariaki, Ohashi Hirofumi, Sato Hiroyuki, Ueta Shohei, Aihara Jun, Goto Minoru, Sumita Junya, Shibata Taiju …

JAEA-Technology 2009-063, 155, Feb, 2010
Irradiation sample fabrications for VHTR; Research and development for advanced high temperature gas-cooled reactor fuels and graphite components (Contract research)

Mozumi Yasuhiro, Ueta Shohei, Aihara Jun, Sawa Kazuhiro

JAEA-Technology 2008-086, 16, Feb, 2009
Development of production technology of ZrC-coated particle, 2 (Contract research)

Yasuda Atsushi, Ueta Shohei, Aihara Jun, Ishibashi Hideharu*, Sawa Kazuhiro

JAEA-Technology 2008-083, 11, Jan, 2009
Development of production technology of ZrC-coated particle, 1 (Contract research)

Yasuda Atsushi, Ueta Shohei, Aihara Jun, Takeuchi Hitoshi, Sawa Kazuhiro

JAEA-Technology 2008-073, 18, Nov, 2008
An Investigation on technical feasibilities of fuel cycle for high temperature gas-cooled reactor (Case study)

Sumita Junya, Ueta Shohei, Aihara Jun, Shibata Taiju, Sawa Kazuhiro

JAEA-Technology 2008-007, 23, Mar, 2008
Calculation of the pressure vessel failure fraction of fuel particle of gas turbine high temperature reactor 300C

Aihara Jun, Ueta Shohei, Mozumi Yasuhiro, Sato Hiroyuki, Motohashi Yoshinobu*, Sawa Kazuhiro

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), 416-422, Sep, 2007
Investigation on inspection methods for ZrC-coated fuel particle; Applicability evaluation of inspection methods for SiC-coated fuel particle

Takayama Tomoo*, Ueta Shohei, Aihara Jun, Yasuda Atsushi*, Ishibashi Hideharu*, Sawa Kazuhiro

JAEA-Research 2007-061, 32, Sep, 2007
Crystal nucleation behavior with annealing of SiC irradiated with Ne above 573K

Aihara Jun, Hojo Kiichi, Furuno Shigemi*, Ishihara Masahiro, Yamamoto Hiroyuki

Proceedings of 8th Asia-Pacific Conference on Electron Microscopy (8APEM) (CD-ROM), 722-723, Jun, 2004

Presentations

Development on extended burnup fuel technologies for practical high temperature gas-cooled reactors; Collaborative research with Kazakhstan

Ueta Shohei, Shibata Taiju, Aihara Jun, Shaimerdenov A.*, Dyussambayev D.*, Takahashi Masashi*, Kinoshita Hideaki*, Gizatulin S.*, Sakaba Nariaki

日本原子力学会2019年秋の大会
Development of security and safety fuel for Pu-burner HTGR, 27; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Mizuta Naoki, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2018年秋の大会
Development of high-strength oxidation-resistant fuel components for high-temperature gas-cooled reactor; Evaluation of mechanical strength properties of fuel compact

Tojo Takuya*, Yamamoto Takenori*, Kuroda Masatoshi*, Aihara Jun, Tachibana Yukio

日本機械学会M\&M2017材料力学カンファレンス
Development of security and safety fuel for Pu-burner HTGR, 21; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2017年秋の大会
Research on advanced fuel element for upgrading safety of high temperature gas-cooled reactors, 4; Modeling for casting oxidation resistant fuel element reactors

Kuroda Masatoshi*, Tojo Takuya*, Yamamoto Takenori*, Aihara Jun, Tachibana Yukio

日本原子力学会2017年秋の大会
Research on advanced fuel element for upgrading safety of high temperature gas-cooled reactors, 2; Development of fabrication technology of oxidation resistant fuel element

Aihara Jun, Ueta Shohei, Honda Masaki*, Ogawa Hiroaki, Shibata Taiju, Mizuta Naoki, Inaba Yoshitomo, Tachibana Yukio

日本原子力学会2017年秋の大会
Investigation to enhance performance of HTGR fuel

Mizuta Naoki, Ueta Shohei, Aihara Jun, Shibata Taiju

平成29年度日本原子力学会北関東支部若手研究者発表会
Development of security and safety fuel for Pu-burner HTGR, 13; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2016年秋の大会
Development of security and safety fuel for Pu-burner HTGR, 10; Evaluation on internal pressure of fuel and nuclear characteristics of reactor core

Goto Minoru, Ueta Shohei, Inaba Yoshitomo, Aihara Jun, Fukaya Yuji, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2016年秋の大会
Consideration of the hot pressing conditions of the high-strength fuel compact for high-temperature gas-cooled reactor

Yamamoto Takenori*, Tojo Takuya*, Kuroda Masatoshi*, Sumita Junya, Aihara Jun, Tachibana Yukio

日本原子力学会2016年秋の大会
Design study on fuel and reactor core for plutonium burner high temperature gas-cooled reactor

Goto Minoru, Inaba Yoshitomo, Fukaya Yuji, Ueta Shohei, Aihara Jun, Tachibana Yukio, Kunitomi Kazuhiko

日本保全学会第13回学術講演会
Nuclear and thermal design for high temperature gas-cooled reactor with SiC matrix fuel

Goto Minoru, Inaba Yoshitomo, Aihara Jun, Ueta Shohei, Tachibana Yukio

日本原子力学会2016年春の年会
Collaboration with Republic of Kazakhstan regarding irradiation performance of HTGR fuel

Ueta Shohei, Aihara Jun, Sumita Junya, Shaimerdenov A.*, Dyussambayev D.*, Gizatulin S.*, Chakrov P.*, Sakaba Nariaki

日本原子力学会2016年春の年会
Development of security and safety fuel for Pu-burner HTGR, 3; Fuel design and nuclear thermal design

Goto Minoru, Ueta Shohei, Aihara Jun, Fukaya Yuji, Inaba Yoshitomo, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2015年秋の大会
Development of security and safety fuel for Pu-burner HTGR, 6; Test and characterization for ZrC coating

Ueta Shohei, Aihara Jun, Tachibana Yukio, Kunitomi Kazuhiko, Okamoto Koji*

日本原子力学会2015年秋の大会
Research and development of clean burn high temperature gas-cooled reactor, 4; Study on fuel fabrication

Ueta Shohei, Aihara Jun, Mizutani Yoshitaka, Ohashi Hirofumi, Sakaba Nariaki, Tachibana Yukio, Kunitomi Kazuhiko

日本原子力学会2013年秋の大会
Conceptual design study of small-sized high temperature gas-cooled reactor for developing countries, 3; Fuel design

Ueta Shohei, Aihara Jun, Mizutani Yoshitaka, Ohashi Hirofumi, Sakaba Nariaki, Tachibana Yukio, Honda Masaki*, Tanaka Hideki*, Furihata Noboru*

日本原子力学会2013年春の年会
Visualization of distribution of lattice defects by a positron microbeam; ZrC coating layers for advanced high temperature gas-cooled reactors

Aihara Jun, Maekawa Masaki, Ueta Shohei, Kawasuso Atsuo, Sawa Kazuhiro

第6回高崎量子応用研究シンポジウム
Evaluation of the zirconium carbide film on the coated fuel particles using a positron microscope

Maekawa Masaki, Yabuuchi Atsushi, Kawasuso Atsuo, Aihara Jun, Sawa Kazuhiro

日本金属学会2011年春期(第148回)大会
Completion of long term high temperature operation with HTTR (High Temperature Engineering Test Reactor), 3; Behaviors of HTTR fuel

Ueta Shohei, Aihara Jun, Inoi Hiroyuki, Umeda Masayuki, Sawa Kazuhiro

日本原子力学会2010年秋の大会