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Volumn 71, Issue 4, 2004, Pages 191-196

Simulation of hypothetical small-break loss-of-coolant accident in modernized nuclear power plant

Author keywords

Accident analysis; Full scope simulator; Nuclear power plant; RELAP5 MOD2

Indexed keywords

ACCIDENT PREVENTION; CHEMICAL REACTORS; COMPUTER SIMULATION; COOLANTS; DATA ACQUISITION; ELECTRIC GENERATORS; ENERGY CONSERVATION; MATHEMATICAL MODELS; PRESSURE EFFECTS; TESTING;

EID: 11244339742     PISSN: 00135852     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article
Times cited : (7)

References (13)
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    • Krajnc, B.1    Boire, R.2    Salim, G.3
  • 5
    • 11244256969 scopus 로고    scopus 로고
    • LOCA analysis for krško full scope simulator verification
    • B. Mavko, L. Cizelj, M. Kovač, Ljubljana, Jožef Stefan Institute and Nuclear Society of Slovenia
    • A. Prošek, I. Parzer, B. Mavko, LOCA Analysis for Krško Full Scope Simulator Verification, B. Mavko, L. Cizelj, M. Kovač, Proceedings of International Conference on Nuclear Energy in Central Europe 2000, pp. 1-9, Ljubljana, Jožef Stefan Institute and Nuclear Society of Slovenia, 2000.
    • (2000) Proceedings of International Conference on Nuclear Energy in Central Europe 2000 , pp. 1-9
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  • 7
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    • NUREG/CR-4312, EGG-2396, Rev.1, Idaho
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  • 8
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    • ANTHEM: Advanced thermal hydraulic model for power plant simulation
    • Lappeenranta, Finland, Technical Research Centre of Finland
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  • 9
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  • 10
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  • 11
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    • Evaluating code uncertainty - II: An optimal statistical estimator method to evaluate the uncertainties of calculated time trends
    • A. Prošek, B. Mavko, Evaluating Code Uncertainty - II: An Optimal Statistical Estimator Method to Evaluate the Uncertainties of Calculated Time Trends, Nuclear Technology, Vol. 126, pp. 186-195, 1999.
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  • 13
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    • Pochard, R.1    Jedrzejewski, F.2    Mazauric, X.3    Carteron, P.Y.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.