ほーはいくあん (Hai Quan Ho) - マイポータル

基本情報

所属: 国立研究開発法人日本原子力研究開発機構

ORCID iD: https://orcid.org/0000-0002-7096-3318
J-GLOBAL ID: 202101005506156632
researchmap会員ID: R000016839

論文

Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code

Irwan Liapto Simanullang, Naoki Nakagawa, Hai Quan Ho, Satoru Nagasumi, Etsuo Ishitsuka, Kazuhiko Iigaki, Nozomu Fujimoto

Annals of Nuclear Energy 177 109314-109314 2022年11月
Calculation of shutdown gamma distribution in the high temperature engineering test reactor

Hai Quan Ho, Toshiaki Ishii, Satoru Nagasumi, Masato Ono, Yosuke Shimazaki, Etsuo Ishitsuka, Minoru Goto, Irwan Liapto Simanullang, Nozomu Fujimoto, Kazuhiko Iigaki

Nuclear Engineering and Design 396 111913-111913 2022年9月
Design of a portable backup shutdown system for the high temperature gas cooled reactor

Shimpei Hamamoto, Hai Quan Ho, Kazuhiko Iigaki, Minoru Goto, Yosuke Shimazaki, Hiroaki Sawahata, Etsuo Ishitsuka

Nuclear Engineering and Design 386 2022年1月
Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments

Nozomu Fujimoto, Kenichi Tada, Hai Quan Ho, Shimpei Hamamoto, Satoru Nagasumi, Etsuo Ishitsuka

Annals of Nuclear Energy 158 2021年8月
Preparation for restarting the high temperature engineering test reactor: Development of utility tool for auto seeking critical control rod position

Hai Quan Ho, Nozomu Fujimoto, Shimpei Hamamoto, Satoru Nagasumi, Minoru Goto, Etsuo Ishitsuka

Nuclear Engineering and Design 377 2021年6月
Feasibility study on tritium recoil barrier for neutron reflectors of research and test reactors

Inesh Kenzhina, Etsuo Ishitsuka, Hai Quan Ho, Naoki Sakamoto, Keisuke Okumura, Noriyuki Takemoto, Yevgeni Chikhray

Fusion Engineering and Design 164 2021年3月
Promising neutron irradiation applications at the high temperature engineering test reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Shoji Takada, Nozomu Fujimoto, Etsuo Ishitsuka

Journal of Nuclear Engineering and Radiation Science 6(2) 2020年4月
Evaluation of tritium release into primary coolant for research and testing reactors

Inesh Kenzhina, Etsuo Ishitsuka, Keisuke Okumura, Hai Quan Ho, Noriyuki Takemoto, Yevgeni Chikhray

Journal of Nuclear Science and Technology 1-12 2020年
Conceptual design of direct ^99mTc production facility at the high temperature engineering test reactor

Hai Quan Ho, Hiroki Ishida, Shimpei Hamamoto, Toshiaki Ishii, Nozomu Fujimoto, Naoyuki Takaki, Etsuo Ishitsuka

Nuclear Engineering and Design 352 2019年10月
Feasibility study of large-scale production of iodine-125 at the high temperature engineering test reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Nozomu Fujimoto, Etsuo Ishitsuka

Applied Radiation and Isotopes 140 209-214 2018年10月
Proposal of a neutron transmutation doping facility for n-type spherical silicon solar cell at high-temperature engineering test reactor

Hai Quan Ho, Yuki Honda, Mizuki Motoyama, Shimpei Hamamoto, Toshiaki Ishii, Etsuo Ishitsuka

Applied Radiation and Isotopes 135 12-18 2018年5月
Investigation of uncertainty caused by random arrangement of coated fuel particles in HTTR criticality calculations

Hai Quan Ho, Yuki Honda, Minoru Goto, Shoji Takada

Annals of Nuclear Energy 112 42-47 2018年2月
Numerical investigation of the random arrangement effect of coated fuel particles on the criticality of HTTR fuel compact using MCNP6

Hai Quan Ho, Yuki Honda, Minoru Goto, Shoji Takada

Annals of Nuclear Energy 103 114-121 2017年5月1日
Benchmark study on realized random packing model for coated fuel particles of HTTR using MCNP6

H. H. Quan, K. Morita, Y. Honda, N. Fujimoto, S. Takada

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年
Neutronic characteristic of HTTR fuel compact with various packing models of coated fuel particle

Ho Hai Quan

JAEA-Technology 2016-040 2016年12月
Design concept for a small pebble bed reactor with ROX fuel

Hai Quan Ho, Toru Obara

Annals of Nuclear Energy 87 471-478 2016年1月1日
Burnup performance of OTTO cycle pebble bed reactors with ROX fuel

Hai Quan Ho, Toru Obara

Annals of Nuclear Energy 83 1-7 2015年9月1日
Impact on burnup performance of coated particle fuel design in pebble bed reactor with ROX fuel

Hai Quan Ho, Toru Obara

International Conference on Nuclear Engineering, Proceedings, ICONE 2015-January 2015年
Composition of ROx fuel for high-burnup pebble bed reactor

Hai Quan Ho, Toru Obara

Transactions of the American Nuclear Society 113 922-923 2015年

MISC

試験研究炉のドライバー燃料から1次冷却材へ放出するトリチウム量の計算

Ho H. Q., 石塚悦男

Physical Sciences and Technology 5(2) 53-56 2019年1月
試験研究炉におけるトリチウム放出源と放出機構

石塚悦男, KENZHINA Inesh, 奥村啓介, HO Hai Quan, 竹本紀之, CHIKHRAY Yevgeni

日本原子力学会秋の大会予稿集(CD-ROM) 2019 2019年
中性子反射体のLi及びU不純物からのトリチウム反跳放出計算

石塚悦男, KENZHINA Inesh, KENZHINA Inesh, 奥村啓介, HO Hai Quan, 竹本紀之, CHIKHRAY Yevgeni

日本原子力研究開発機構JAEA-Technology(Web) (2018-010) 2018年

ほーはいくあん

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