Full metadata record
DC Field | Value | Language |
---|---|---|
dc.contributor.author | 제무성 | - |
dc.date.accessioned | 2017-07-21T02:45:26Z | - |
dc.date.available | 2017-07-21T02:45:26Z | - |
dc.date.issued | 2015-10 | - |
dc.identifier.citation | Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, Korea, October 29-30, 2015, Page. 1-3 | en_US |
dc.identifier.uri | http://www.kns.org:8115/kns_files/34/15A-410%EA%B9%80%EB%82%A8%EC%98%81.pdf | - |
dc.identifier.uri | http://hdl.handle.net/20.500.11754/27984 | - |
dc.description.abstract | After the Chernobyl nuclear accident, mainly in Sweden, Germany, France, Switzerland, the Netherlands and other European countries have installed CFVS. In the US, some Boiling Water Reactor type only the voluntary installation of CFVS was required. But until now it has not been installed for pressurized water reactors. In Korea, CFVS is currently installed on Wolseong Unit 1 and preferentially applied to Heavy Water Reactor. Later it plans to apply for the Light Water Reactor. In this study, a safety improvement of installing the CFVS was assessed by the tool of Probabilistic Safety Assessment (PSA) for a reference plant. The CFVS is under installment in CANDU reactor for preventing the containment failure during severe accidents. But it has been evaluated that the effectiveness is negligible because of adverse effects of radioactive nuclides releases. Now the CFVS has not been installed yet in the LWR. The results can vary greatly depending on the detailed assessment | en_US |
dc.description.sponsorship | This research was supported by a grant from the Nuclear Safety Research Program of the Korea Radiation Safety Foundation, with funding by the Korean government's Nuclear Safety and Security Commission (Grant Code: 1305008-0113-SB110), Institute for Basic Science and Innovative Technology Center for Radiation Safety. | en_US |
dc.language.iso | en | en_US |
dc.publisher | KNS | en_US |
dc.subject | CONTAINMENT | en_US |
dc.subject | FILTERS | en_US |
dc.subject | FISSION PRODUCTS | en_US |
dc.subject | PROBABILITY | en_US |
dc.subject | PWR TYPE REACTORS | en_US |
dc.subject | REACTOR ACCIDENTS | en_US |
dc.subject | SAFETY ANALYSIS | en_US |
dc.title | A Probabilistic Methodology for Assessing the Effectiveness of the Containment Filtered Venting Systems | en_US |
dc.type | Article | en_US |
dc.relation.page | 1-3 | - |
dc.contributor.googleauthor | Kim, Namyeong | - |
dc.contributor.googleauthor | Jae, Moosung | - |
dc.sector.campus | S | - |
dc.sector.daehak | COLLEGE OF ENGINEERING[S] | - |
dc.sector.department | DEPARTMENT OF NUCLEAR ENGINEERING | - |
dc.identifier.pid | jae | - |
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