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dc.contributor.author제무성-
dc.date.accessioned2016-11-01T07:42:37Z-
dc.date.available2016-11-01T07:42:37Z-
dc.date.issued2015-03-
dc.identifier.citationATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, v. 60, NO 3, Page. 173-182en_US
dc.identifier.issn1431-5254-
dc.identifier.urihttp://hdl.handle.net/20.500.11754/24037-
dc.identifier.urihttps://inis.iaea.org/search/search.aspx?orig_q=RN:46063038-
dc.description.abstractThe System-Integrated Modular Advanced Reactor (SMART) that has been recently designed in KOREA and has acquired standard design certification from the nuclear power regulatory body (NSSC) is an integral type reactor with 330MW thermal power. It is a small sized reactor in which the core, steam generator, pressurizer, and reactor coolant pump that are in existing pressurized light water reactors are designed to be within a pressure vessel without any separate pipe connection. In addition, this reactor has much different design characteristics from existing pressurized light water reactors such as the adoption of a passive residual heat removal system and a cavity flooding system. Therefore, the safety of the SMART against severe accidents should be checked through severe accident analysis reflecting the design characteristics of the SMART. For severe accident analysis, en analysis model has been developed reflecting the design information presented in the standard design safety analysis report. The severe accident analysis model has been developed using the MELCOR code that is widely used to evaluate pressurized LWR severe accidents. The steady state accident analysis model for the SMART has been simulated. According to the analysis results, the developed model reflecting the design of the SMART is found to be appropriate. Severe accident analysis has been performed for the representative accident scenarios that lead to core damage to check the appropriateness of the severe accident management plan for the SMART The SMART has been shown to be safe enough to prevent severe accidents by utilizing severe accident management systems such as a containment spray system, a passive hydrogen recombiner, and a cavity flooding system. In addition, the SMART is judged to have been technically improved remarkably compared to existing PWRs. The SMART has been designed to have a larger reactor coolant inventory compared to its core's thermal power, a large surface area in the lower hemisphere of the reactor pressure vessel assembly, and a large free volume in the containment building.en_US
dc.description.sponsorshipThis work was supported by a National Research Foundation of Korea grant funded by the Ministry of Science, ICT & Future Planning and partly supported by a grant from the Nuclear Safety Research Program of the Korea Radiation Safety Foundation under NSSC.en_US
dc.language.isoenen_US
dc.publisherINFORUM VERLAGS-VERWALTUNGSGESELLSCHAFT MBHen_US
dc.subjectACCIDENT MANAGEMENT-
dc.subjectCOMPUTERIZED SIMULATION-
dc.subjectCONTAINMENT BUILDINGS-
dc.subjectCONTAINMENT SPRAY SYSTEMS-
dc.subjectLOSS OF COOLANT-
dc.subjectM CODES-
dc.subjectMODULAR STRUCTURES-
dc.subjectPRESSURE VESSELS-
dc.subjectPWR TYPE REACTORS-
dc.subjectREACTOR CORES-
dc.subjectREACTOR SAFETY-
dc.subjectREPUBLIC OF KOREA-
dc.subjectSTEADY-STATE CONDITIONS-
dc.subjectSURFACE AREA-
dc.titleA Severe Accident Analysis for the System-Integrated Modular Advanced Reactoren_US
dc.typeArticleen_US
dc.relation.no3-
dc.relation.volume60-
dc.relation.page173-173-
dc.relation.journalATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER-
dc.contributor.googleauthorJung, Gunhyo-
dc.contributor.googleauthorJae, Moosung-
dc.relation.code2015001565-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidjae-
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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