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Journal of Nuclear Science and Technology | 2009

Plant Simulation System for Developing ABWR Automatic Power Regulator System

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

Development of Instrumentation System for Severe Accidents

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

Reactor Water-Level/Temperature Measurement Apparatus

Atsushi Fushimi; Atsushi Baba; Izumi Yamada; Setsuo Arita; Masaki Kanada; Akira Murata; Tamotsu Asano; Mikio Koyama; Hiroaki Katsuyama; Ryuta Hama; Itsuki Naito


Archive | 2007

Reactor power control apparatus of a natural circulation boiling water reactor and a feed water control apparatus and nuclear power generation plant

Atsushi Fushimi; Setsuo Arita; Kazuhiko Ishiii; Yoshihiko Ishii; Shin Hasegawa; Atsutoshi Mizuide


Archive | 2011

Nuclear reactor system and nuclear reactor control method

Atsushi Fushimi; Setsuo Arita; Yoshihiko Ishii; Tomohiko Ikegawa; Shin Hasegawa; Kazuhiko Ishii


Archive | 2005

Neutron instrumentation system in nuclear power plant

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

Neutron Monitoring System

Atsushi Fushimi


Archive | 2010

TEMPERATURE DETECTION APPARATUS FOR NATURAL CIRCULATION BOILING WATER REACTOR

Yoshihiko Ishii; Shiro Takahashi; Setsuo Arita; Atsushi Fushimi; Tomohiko Ikegawa


Archive | 2008

DEVICE AND METHOD FOR ASSESSING EFFECT OF MOTOR SYSTEM IN PLANT

Atsushi Fushimi; Tomotaka Sakata; Hirohisa Satomi; Izumi Yamada; 篤 伏見; 智貴 坂田; 泉 山田; 弘久 里見


Archive | 2006

Nuclear reactor monitoring device and output controller

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

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