Search Results - "Nagasumi, Satoru"

Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor by Koga, Yuki, Matsuura, Hideaki, Ida, Yuma, Okamoto, Ryo, Katayama, Kazunari, Otsuka, Teppei, Goto, Minoru, Nakagawa, Shigeaki, Nagasumi, Satoru, Ishitsuka, Etsuo, Shimazaki, Yosuke

“…•Tritium production using high temperature gas-cooled reactor (HTGR) is considered.•An irradiation test on High Temperature engineering Test Reactor (HTTR) is…”
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Current status of high temperature gas-cooled reactor development in Japan by Nagatsuka, Kentaro, Noguchi, Hiroki, Nagasumi, Satoru, Nomoto, Yasunobu, Shimizu, Atsushi, Sato, Hiroyuki, Nishihara, Tetsuo, Sakaba, Nariaki

“…•JAEA has conducted considerable works on the R&Ds of HTGR technologies through design, construction, operation, and maintenance of HTTR.•HTTR heat application…”
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Preparation for restarting the high temperature engineering test reactor: Development of utility tool for auto seeking critical control rod position by Ho, Hai Quan, Fujimoto, Nozomu, Hamamoto, Shimpei, Nagasumi, Satoru, Goto, Minoru, Ishitsuka, Etsuo

“…•A new utility tool was developed for auto-seeking critical control rod position.•Fuel temperature was calculated using a priori single-channel…”
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Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor by Ho, Hai Quan, Ishii, Toshiaki, Nagasumi, Satoru, Ono, Masato, Shimazaki, Yosuke, Ishitsuka, Etsuo, Sawahata, Hiroaki, Goto, Minoru, Simanullang, Irwan Liapto, Fujimoto, Nozomu, Iigaki, Kazuhiko

“…•Feasibility of using BeO as secondary neutron source was investigated.•Neutron flux at ex-neutron detector is high enough even after 5 years shutdown.•Adding…”
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Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments by Fujimoto, Nozomu, Tada, Kenichi, Quan Ho, Hai, Hamamoto, Shimpei, Nagasumi, Satoru, Ishitsuka, Etsuo

“…•Code-to-experiment verification of FRENDY was carried out.•ACE files of JENDL-4.0 and ENDF/B-VII.1 were processed by FRENDY.•Various criticality benchmarks of…”
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Calculation of shutdown gamma distribution in the high temperature engineering test reactor by Ho, Hai Quan, Ishii, Toshiaki, Nagasumi, Satoru, Ono, Masato, Shimazaki, Yosuke, Ishitsuka, Etsuo, Goto, Minoru, Simanullang, Irwan Liapto, Fujimoto, Nozomu, Iigaki, Kazuhiko

“…•Shutdown gamma heat is calculated by coupling MCNP6 and ORIGEN2.•There is a good agreement in decay gamma emission from HTTR fuel between calculation and…”
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Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code by Simanullang, Irwan Liapto, Nakagawa, Naoki, Quan Ho, Hai, Nagasumi, Satoru, Ishitsuka, Etsuo, Iigaki, Kazuhiko, Fujimoto, Nozomu

“…•Power distribution plays a significant role in high-temperature gas-cooled reactors.•Experiments for measuring the power distribution were performed at the…”
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