| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 8070553 | Annals of Nuclear Energy | 2013 | 10 Pages |
Abstract
⺠The analysis was performed from the viewpoint of primary coolant leakage. ⺠The thermal hydraulic responses and the maximum leakage have been identified. ⺠There is no direct release into the atmosphere caused by an SGTR accident. ⺠SMART safety system works well against an SGTR accident.
Keywords
SCsSGTRLoss of Offsite PowerMSSVSafety injection systemPRHRSNSSSMDNBRMSIVPWRMTCRCSMSISRCPSMRFTCSISCSSSafety injectionLoopPressurized Water ReactorPassive residual heat removal systemReactor coolant systemModerator temperature coefficientFuel temperature coefficientKorea Atomic Energy Research InstituteSMARTThermal-hydraulicSteam Generator Tube RuptureReactor coolant pumpSteam generatorKAERI
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Hee-Kyung Kim, Soo Hyoung Kim, Young-Jong Chung, Hyeon-Soo Kim,