Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
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C.-L. Yu
Abstract
This paper presents analytical investigations of the cut-off diameter of aerosol particle for filtered containment venting system in a nuclear power plant. These analyses were done for operation conditions of the containment venting and the numerical results reveal that the particle sizes of fission products released to environment range between 10−8 m and 10−5 m and mostly distribute between 10−7 m and 10−6 m. For designing a filtered containment venting system, the collection efficiency of the filter must be high-quality in the main range 10−7 m – 10−6 m. In this research, the numerical results can offer nuclear power plant a useful reference to design and set up FCVS.
Kurzfassung
In diesem Beitrag werden analytische Untersuchungen zum Cut-Off-Durchmesser von Aerosolpartikeln für das gefilterte Containment-Entlüftungssystem in einem Kernkraftwerk vorgestellt. Diese Analysen wurden für die Betriebsbedingungen der Containment-Entlüftung durchgeführt und die numerischen Ergebnisse zeigen, dass die Partikelgrößen der in die Umgebung freigesetzten Spaltprodukte zwischen 10−8 m und 10−5 m liegen und sich meist zwischen 10−7 m und 10−6 m verteilen. Für die Auslegung eines gefilterten Containment-Entlüftungssystems muss der Abscheidegrad des Filters im Hauptbereich 10−7 m – 10−6 m hochwertig sein. In dieser Forschung können die numerischen Ergebnisse dem Kernkraftwerk eine nützliche Referenz für die Auslegung und Einrichtung von FCVS bieten.
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© 2019, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
- Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
- Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
- Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
- Effect of reactor operator intervention during unprotected LOFA in a typical MTR
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
- Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
- Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
- Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
- Effect of reactor operator intervention during unprotected LOFA in a typical MTR
