ほーはいくあん

ホ- ハイクアン | Ho Hai Quan

所属機関・部署：
論文 (19件)：

Irwan Liapto Simanullang, Naoki Nakagawa, Hai Quan Ho, Satoru Nagasumi, Etsuo Ishitsuka, Kazuhiko Iigaki, Nozomu Fujimoto. Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code. Annals of Nuclear Energy. 2022. 177. 109314-109314
Hai Quan Ho, Toshiaki Ishii, Satoru Nagasumi, Masato Ono, Yosuke Shimazaki, Etsuo Ishitsuka, Minoru Goto, Irwan Liapto Simanullang, Nozomu Fujimoto, Kazuhiko Iigaki. Calculation of shutdown gamma distribution in the high temperature engineering test reactor. Nuclear Engineering and Design. 2022. 396. 111913-111913
Shimpei Hamamoto, Hai Quan Ho, Kazuhiko Iigaki, Minoru Goto, Yosuke Shimazaki, Hiroaki Sawahata, Etsuo Ishitsuka. Design of a portable backup shutdown system for the high temperature gas cooled reactor. Nuclear Engineering and Design. 2022. 386
Nozomu Fujimoto, Kenichi Tada, Hai Quan Ho, Shimpei Hamamoto, Satoru Nagasumi, Etsuo Ishitsuka. Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments. Annals of Nuclear Energy. 2021. 158
Hai Quan Ho, Nozomu Fujimoto, Shimpei Hamamoto, Satoru Nagasumi, Minoru Goto, Etsuo Ishitsuka. Preparation for restarting the high temperature engineering test reactor: Development of utility tool for auto seeking critical control rod position. Nuclear Engineering and Design. 2021. 377

MISC (3件)：

Ho H. Q., 石塚悦男. 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. Physical Sciences and Technology. 2019. 5. 2. 53-56
石塚悦男, KENZHINA Inesh, 奥村啓介, HO Hai Quan, 竹本紀之, CHIKHRAY Yevgeni. 試験研究炉におけるトリチウム放出源と放出機構. 日本原子力学会秋の大会予稿集(CD-ROM). 2019. 2019
石塚悦男, KENZHINA Inesh, KENZHINA Inesh, 奥村啓介, HO Hai Quan, 竹本紀之, CHIKHRAY Yevgeni. 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. 日本原子力研究開発機構JAEA-Technology(Web). 2018. 2018-010

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ほー はいくあん