フィルタベント性能評価のための基盤技術の開発と活用
概要
When an excess pressure and temperature are added to a containment vessel (CV) of a nuclear power plant (NPP) by a severe accident, overpressure damage of the CV is assumed to be possible. When the CV falls into such a situation, radioactive materials in the CV are released into the environment. Filtered containment venting systems (FCVS) that is installed in the exhaust systems reduce pressure in the CV while mitigating the release of the radioactive materials by the multi-scrubbers (venturi-scrubber, wet scrubbing, static mixer, metal-fiber filter and molecular sieve). Hence, the radioactive materials in the CV venting are emitted in various forms (CsI / CsOH aerosol, I2 gas, CH3I gas and so on) and these materials is carried by steam-based gas. This study has developed technical basis, data-base and empirical model of FCVS performance.
