This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFVS) for a long operating time using the MELCOR computer code. The modeling of the CFVS, including the models for pool scrubbing and the filter, was added to the input file for the OPR-1000, and a Station Blackout (SBO) was chosen as an accident scenario. Although depressurization in the containment building as a primary objective of the CFVS was successful, the decontamination feature by scrubbing and filtering in the CFVS for a long operating time could fail by the continuous evaporation of the scrubbing solution. After the operation of the CFVS, the atmosphere temperature in the CFVS became slightly above the water saturation temperature owi...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
The Westinghouse Nuclear Safety Advisory Letter NSAL-09-8 investigated the possibility of presence o...
As an additional safety measure in the new 700 MWe Indian pressurized heavy water reactors, the firs...
This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFV...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
The integrity of the containment will be challenged during a severe accident due to pressurization c...
Accident sequences from WASH-1400 were selected and analyzed with the MARCH/CORRAL code to provide a...
For the Korean design of the PCCS (passive containment cooling system) in an innovative PWR, the ove...
In the unlikely event of a nuclear power plant long duration station black-out, as in the Fukushima ...
International audienceDuring the course of a severe accident in a nuclear power plant, water can be ...
Due to the Three Mile Island accident in 1979 the Swedish government took the decision in 1986 to im...
The formation, size and distribution of non-condensable gas bubbles in the condensation pool of the ...
Containment building is the final barrier for radioactive releases from a nuclear power plant (NPP)....
Due to the character of the original source materials and the nature of batch digitization, quality ...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
The Westinghouse Nuclear Safety Advisory Letter NSAL-09-8 investigated the possibility of presence o...
As an additional safety measure in the new 700 MWe Indian pressurized heavy water reactors, the firs...
This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFV...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europ...
The integrity of the containment will be challenged during a severe accident due to pressurization c...
Accident sequences from WASH-1400 were selected and analyzed with the MARCH/CORRAL code to provide a...
For the Korean design of the PCCS (passive containment cooling system) in an innovative PWR, the ove...
In the unlikely event of a nuclear power plant long duration station black-out, as in the Fukushima ...
International audienceDuring the course of a severe accident in a nuclear power plant, water can be ...
Due to the Three Mile Island accident in 1979 the Swedish government took the decision in 1986 to im...
The formation, size and distribution of non-condensable gas bubbles in the condensation pool of the ...
Containment building is the final barrier for radioactive releases from a nuclear power plant (NPP)....
Due to the character of the original source materials and the nature of batch digitization, quality ...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
The Westinghouse Nuclear Safety Advisory Letter NSAL-09-8 investigated the possibility of presence o...
As an additional safety measure in the new 700 MWe Indian pressurized heavy water reactors, the firs...