Fukushima Daiichi NPP accident would be terminated, if sufficient accident countermeasures, such as water proof door, mobile power, etc. In case of Europe, it had already installed the heat removal system and filtered containment venting system (FCVS) from the lessons of TMI and Chernobyl Accidents. The new regulatory standard, the filtered vent system (FCVS) should be installed, and prevent the radioactive material in case of the severe accident and the overpressure breakage prevention of a primary co...
英字タイトル:
Development of High Efficiency Filtered Containment Venting System by using AgX

FuNushima Daiichi NPP accident would be terminated, if sufficient accident countermeasures, such as water proof door, mobile power, etc. In case of Europe, it had already installed the heat removal system and filtered containment venting system (FCVS) from the lessons o f TMI and Chernobyl Accidents. Decay heat removal system and CV spray cooling system with FCVS are ensured by using mobile generators and heat exchangers to Neep the ultimate heat sinN even in any natural disaster, such as large earthquaNe,...
英字タイトル:
Development of High Efficiency Filtered Containment Venting System by using AgX

In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in FuNushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, decay heat em ted from fuels in reactor core was calculated. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. We analyzed IC with TRAC code. We made an experiment in order to checN IC’s input data. Because analysis data is close to experimental data, we made sure validity of inpu...
英字タイトル:
Evaluation on Decay Heat Removal Capability of Isolation Condenser for Depressurization and Cooling System

In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in Fukushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, we calculated decay heat which was emitted from core. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. Analysis was conducted with TRAC code. We made an experiment in order to check input data for IC. Because analysis data was close to experimental data, we made sure of valid...
英字タイトル:
Study of Easing Severe Accident by Using Isolation Condenser

Wastage phenomena occur when a heat transfer tube is failed in a Steam Generator (SG) of Fast Breeder Reactor (FBR) and its mechanism is still unexplained. We focused on Liquid Droplet Impingement Erosion (LDIE) as a factor of the wastage phenomena and performed a basic study with a partial mock-up water test simulating a piping group in SG for quantitative evaluation of LDIE. First, we did visualization tests of high pressure and high speed jet into water. The test section consists of a failure heat ...
英字タイトル:
Study on Rapid Wastage due to Liquid Droplet Impingement on Heat Transfer Tube in SG of Fast Breeder Reactor