Aerosols behavior inside a PWR during an accident
Description
During very hypothetical accidents occurring in a pressurized water ractor, radioactive aerosols can be released, during core-melt, inside the reactor containment building. A good knowledge of their behavior in the humid containment atmosphere (mass concentration and size distribution) is essential in order to evaluate their harmfulness in case of environment contamination and to design possible filtration devices. Accordingly the Safety Analysis Department of the Atomic Energy Commission uses several computer models, describing the particle formation (BOIL/MARCH), then behavior in the primary circuits (TRAP-MELT), and in the reactor containment building (AEROSOLS-PARFDISEKO-III B). On the one hand, these models have been improved, in particular the one related to the aerosol formation (nature and mass of released particles) using recent experimental results. On the other hand, sensitivity analyses have been performed with the AEROSOLS code which emphasize the particle coagulation parameters: agglomerate shape factors and collision efficiency. Finally, the different computer models have been applied to the study of aerosol behavior during a 900 MWe PWR accident: loss-of-coolant-accident (small break with failure of all safety systems)
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
Au cours d'accidents tres hypothetiques survenant dans un reacteur nucleaire a eau pressurisee, des aerosols radioactifs peuvent etre emis, lors de la fusion du combustible, dans l'enceinte de confinement. Une bonne connaissance de leur comportement dans l'atmosphere humide de l'enceinte (concentration massique et granulometrie) est indispensable afin d'evaluer leur nocivite en cas de transfert intempestif dans l'environnement et dimensionner d'eventuels dispositifs de filtration. Ainsi, le Departement d'Analyse de Surete du Commissariat a l'Energie Atomique dispose de codes de calcul, modelisant la formation des aerosols (BOIL/MARCH), leur evolution dans le circuit primaire (TRAP-MELT) et dans l'enceinte (AEROSOLS-PARDISEKO III B). D'une part, nous avons ameliore ces modeles, particulierement celui relatif a la formation des aerosols (nature et masse des matieres liberees) au moyen de resultats experimentaux recents. D'autre part, nous avons mene une etude de sensibilite (avec le code AEROSOLS) dont les resultats soulignent l'importance des parametres lies a la coagulation des particules: facteurs de forme des agglomerats et efficacite de collision. Enfin, les differents codes de calcul ont ete appliques a l'etude du comportement des aerosols dans le cas d'un accident sur un reacteur 900 Mwe: perte du fluide de refroidissement du coeur (petite breche sur le circuit primaire avec defaillance de tous les systemes de sauvegarde)Files
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Additional details
Additional titles
- Original title (French)
- Comportement des aerosols dans un reacteur PWR en cas d'accident
Publishing Information
- Imprint Pagination
- 211 p.
- Report number
- CEA-R--5230
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 15006821
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- A CODES; CESIUM; CHEMICAL COMPOSITION; COLLISIONS; COMPUTER CODES; CONTAINMENT BUILDINGS; IODINE; KINETICS; LOSS OF COOLANT; M CODES; MASS; MELTDOWN; P CODES; PARTICLE SIZE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; QUANTITY RATIO; RADIOACTIVE AEROSOLS; SENSITIVITY ANALYSIS; T CODES; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; AEROSOLS; ALKALI METALS; BUILDINGS; COLLOIDS; CONTAINMENT; COOLING SYSTEMS; DISPERSIONS; ELEMENTS; HALOGENS; METALS; NONMETALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIZE; SOLS; WATER COOLED REACTORS; WATER MODERATED REACTORS