Atsushi Fushimi
Hitachi
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Publication
Featured researches published by Atsushi Fushimi.
Journal of Nuclear Science and Technology | 2009
Yoshihiko Ishii; Atsushi Fushimi; Setsuo Arita; Hitoshi Ochi
We developed a plant simulation code system to design and verify an automatic power regulator (APR) system for an advanced boiling water reactor (ABWR). The point kinetic plant simulator AUTSIMU is an off-line and real-time online plant simulation code that can simulate the start-up process from a subcritical condition of cold water to a 100% rated power condition as well as the reactor shutdown process. The three-dimensional effect of neutron detector signals in the core was simulated by combining predetermined three-dimensional analysis and point kinetic analysis results. The AUTSIMU code was tested using ABWR start-up experimental data. The calculated results were in good agreement with the measured ones. Less than one minute was needed in the off-line mode to simulate a ten-hour transient with an ordinary personal computer. We confirmed that simple AUTSIMU models could effectively simulate ABWR start-up behaviors. The APR hardware was effectively verified in the online mode through factory tests before being shipped to the nuclear site.
Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events | 2014
Shohei Wada; Akira Murata; Setsuo Arita; Atsushi Fushimi; Hirotsugu Suzuki; Yasutake Fujishima
The accident at Tokyo Electric Power Company’s Fukushima Dai-ichi Nuclear Power Plant (TF-1 accident) caused severe situations and resulted in a difficulty to measure important parameters to monitor plant conditions. Therefore, we have studied to select the important parameters (SA parameters) that should be monitored at the severe accident and are developing the Severe Accident Instrumentations and Monitoring Systems (SA-keisou) that could measure the parameters in severe accident conditions. (SA-keisou in Japanese means “severe accident instrumentation and monitoring systems). In this study, the boiled water reactor (BWR) is mainly explained.This study is a part of the results of the collaborative project by domestic electric power companies and plant manufacturers that is carried out as the Safety Enhancement for LWRs program by Agency for Natural Resources and Energy.Copyright
Archive | 2012
Atsushi Fushimi; Atsushi Baba; Izumi Yamada; Setsuo Arita; Masaki Kanada; Akira Murata; Tamotsu Asano; Mikio Koyama; Hiroaki Katsuyama; Ryuta Hama; Itsuki Naito
Archive | 2007
Atsushi Fushimi; Setsuo Arita; Kazuhiko Ishiii; Yoshihiko Ishii; Shin Hasegawa; Atsutoshi Mizuide
Archive | 2011
Atsushi Fushimi; Setsuo Arita; Yoshihiko Ishii; Tomohiko Ikegawa; Shin Hasegawa; Kazuhiko Ishii
Archive | 2005
Setsuo Arita; Atsushi Fushimi; Shoichi Matsumiya; Tomotaka Sakata; 篤 伏見; 智貴 坂田; 節男 有田; 章一 松宮
Archive | 2014
Atsushi Fushimi
Archive | 2010
Yoshihiko Ishii; Shiro Takahashi; Setsuo Arita; Atsushi Fushimi; Tomohiko Ikegawa
Archive | 2008
Atsushi Fushimi; Tomotaka Sakata; Hirohisa Satomi; Izumi Yamada; 篤 伏見; 智貴 坂田; 泉 山田; 弘久 里見
Archive | 2006
Setsuo Arita; Atsushi Fushimi; Makoto Hasegawa; Tomohiko Ikegawa; Yoshihiko Ishii; 篤 伏見; 節男 有田; 智彦 池側; 佳彦 石井; 真 長谷川