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Volumn , Issue , 2004, Pages 1393-1401

Periodic safety review on safety analyses of Kori nuclear units 3,4

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CREEP; FAILURE ANALYSIS; HEATING; LOSS OF COOLANT ACCIDENTS; REGULATORY COMPLIANCE; STANDARDS;

EID: 14844360447     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (1)

References (22)
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  • 5
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    • Study on time delay between loss of offsite power and turbine trip in safety analysis
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  • 6
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    • Personal communication with Professor Kyuho Kim, Ansan College of Technology
    • Personal communication with Professor Kyuho Kim, Ansan College of Technology.
  • 7
    • 14844349312 scopus 로고    scopus 로고
    • A prioritization of generic safety issues
    • U.S. Nuclear Regulatory Commission
    • R. EMRIT, R. RIGGS, W. MILSTEAD, J. PITTMAN, and H. VANDERMOLEN, "A Prioritization of Generic Safety Issues," NUREG-0933, U.S. Nuclear Regulatory Commission (2000).
    • (2000) NUREG-0933
    • Emrit, R.1    Riggs, R.2    Milstead, W.3    Pittman, J.4    Vandermolen, H.5
  • 9
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    • Section III, Division 1, Subsection NB-3113 Service Conditions, American Society of Mechanical Engineers (ASME)
    • J. HECHMER, ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB-3113 Service Conditions), American Society of Mechanical Engineers (ASME) (2000).
    • (2000) ASME Boiler and Pressure Vessel Code
    • Hechmer, J.1
  • 11
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    • Regulatory effectiveness of the anticipated transient without scram rule
    • U.S. Nuclear Regulatory Commission
    • W. S. RAUGHLEY and G. F. LANIK, "Regulatory Effectiveness of the Anticipated Transient Without Scram Rule," NUREG-1780, U.S. Nuclear Regulatory Commission (2003).
    • (2003) NUREG-1780
    • Raughley, W.S.1    Lanik, G.F.2
  • 12
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    • Loss of residual heat removal system, diablo canyon unit 2
    • U.S. Nuclear Regulatory Commission
    • USNRC INSPECTION TEAM, "Loss of Residual Heat Removal System, Diablo Canyon Unit 2," NUREG-1269, U.S. Nuclear Regulatory Commission (1987).
    • (1987) NUREG-1269
  • 14
    • 14844363183 scopus 로고    scopus 로고
    • Safety analysis under midloop operation in Korea nuclear units #5,6
    • Korea Electric Power Research Institute
    • D. J. YUN and H. S. OH, "Safety Analysis under Midloop Operation in Korea Nuclear Units #5,6," Technical Memo 01NS12.P2003.129, Korea Electric Power Research Institute (2003).
    • (2003) Technical Memo 01NS12.P2003.129
    • Yun, D.J.1    Oh, H.S.2
  • 15
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    • App. 19.1 rapid depressurization capability
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  • 19
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    • App. 8.2-2 review guide on alternative AC power source for station blackout
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    • KINS, "App. 8.2-2 Review Guide on Alternative AC Power Source for Station Blackout," Safety Review Guide (SRG), Korea Institute of Nuclear Safety (KINS) (1999).
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  • 21
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  • 22
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    • Severe accident management guidance technical basis report
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    • Henry, R.E.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.