{"title":"Risk assessment of the beneficial impact of a filtered venting containment system in a PWR with large, dry containment","authors":"Rafael Schechtman , Carolyn D. Heising","doi":"10.1016/0306-4549(95)00046-1","DOIUrl":null,"url":null,"abstract":"<div><div>Many of the potential high consequence Class-9 accidents in pressurized water reactors (PWRs) involve containment failure by overpressurization. Filtered Venting Containment Systems (FVCS) have been suggested to prevent this mode of containment failure and to reduce the radioactive releases. This study quantified the beneficial effect of an FVCS on the risk to the public from accidents in a PWR with a large, dry containment (Surry-plant). The accidents considered were those found to be the most likely to cause containment failure by overpressurization. The results for those dominant accidents were then used to infer the risk reduction potential of the FVCS. This study developed a phenomenological event tree to characterize the ex-vessel accident scenarios which might be encountered by the FVCS. The phenomena considered in the tree and their consequences received supportive analyses, including the pressure vessel failure, the melt release from the vessel, the occurrence of ex-vessel events, with and without the operation of the FVCS.</div><div>The point estimate results obtained in this study show that, for the PWR design considered, the FVCS reduces the risks of early and latent fatalities by one order of magnitude. Only a marginal reduction is attained for the risk of property damage. Uncertainty analysis indicated that values of approx. <span><math><mtext>1</mtext><mtext>10</mtext></math></span> of the point estimate results are regarded as more likely. The uncertainty in the other direction is not likely to be greater than a factor of 2.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"23 8","pages":"Pages 641-661"},"PeriodicalIF":2.3000,"publicationDate":"1996-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0306454995000461","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"1999/10/6 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Many of the potential high consequence Class-9 accidents in pressurized water reactors (PWRs) involve containment failure by overpressurization. Filtered Venting Containment Systems (FVCS) have been suggested to prevent this mode of containment failure and to reduce the radioactive releases. This study quantified the beneficial effect of an FVCS on the risk to the public from accidents in a PWR with a large, dry containment (Surry-plant). The accidents considered were those found to be the most likely to cause containment failure by overpressurization. The results for those dominant accidents were then used to infer the risk reduction potential of the FVCS. This study developed a phenomenological event tree to characterize the ex-vessel accident scenarios which might be encountered by the FVCS. The phenomena considered in the tree and their consequences received supportive analyses, including the pressure vessel failure, the melt release from the vessel, the occurrence of ex-vessel events, with and without the operation of the FVCS.
The point estimate results obtained in this study show that, for the PWR design considered, the FVCS reduces the risks of early and latent fatalities by one order of magnitude. Only a marginal reduction is attained for the risk of property damage. Uncertainty analysis indicated that values of approx. of the point estimate results are regarded as more likely. The uncertainty in the other direction is not likely to be greater than a factor of 2.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.