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Volumn 2006, Issue , 2006, Pages 1066-1077

Application of advanced thermal hydraulic TRACG model to preserve operating margins in BWRs at extended power uprate conditions

Author keywords

[No Author keywords available]

Indexed keywords

BENCHMARKING; CONDITION MONITORING; HYDRAULIC MODELS; MACHINE DESIGN; NUCLEAR REACTOR LICENSING; UNCERTAIN SYSTEMS;

EID: 33845771339     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (14)

References (20)
  • 7
    • 0012482956 scopus 로고
    • Quantifying reactor safety margins: Application of code scaling, applicability, and uncertainty evaluation methodology to a large-break loss-of-coolant accident
    • December
    • B. Boyack et. al., " Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation methodology to a Large-Break Loss-of-Coolant Accident", NUREG/CR-5249, December 1989.
    • (1989) NUREG/CR-5249
    • Boyack, B.1
  • 8
    • 84962639876 scopus 로고
    • Best-estimate calculation of emergency core cooling system performance
    • U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May
    • U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Regulatory Guide 1.157, " Best-Estimate Calculation of Emergency Core Cooling System Performance", May 1989.
    • (1989) Regulatory Guide 1.157
  • 9
    • 27744526422 scopus 로고    scopus 로고
    • Transient and accident analysis methods
    • U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, December
    • U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Draft Regulatory Guide DG-1120, " Transient and Accident Analysis Methods", December 2002.
    • (2002) Draft Regulatory Guide , vol.DG-1120
  • 11
    • 33845737387 scopus 로고
    • TRAC-BF1/mod1 models and correlations
    • Idaho National Engineering Laboratory, August
    • J. A. Borkowski, et al., " TRAC-BF1/Mod1 Models and Correlations", NUREG/CR-4391, Idaho National Engineering Laboratory, August 1992.
    • (1992) NUREG/CR-4391
    • Borkowski, J.A.1
  • 12
    • 33845784705 scopus 로고
    • BWR REFILL/REFLOOD program task 4.7 - Model development for the BWR version of TRAC
    • GEAP-22051, EPRI NP-2375, April
    • J. G. M. Andersen, K. H. Chu and J. C. Shaug, " BWR REFILL/REFLOOD Program Task 4.7 - Model Development for the BWR version of TRAC", GEAP-22051, NUREG/CR-2573, EPRI NP-2375, April 1983.
    • (1983) NUREG/CR-2573
    • Andersen, J.G.M.1    Chu, K.H.2    Shaug, J.C.3
  • 13
    • 84915486803 scopus 로고
    • BWR REFILL/REFLOOD program task 4.7 - TRAC-BWR component models
    • GEAP-22052, EPRI NP-2376, April
    • Y. K. Cheung, V. Parameswaran and J. C. Shaug, " BWR REFILL/REFLOOD Program Task 4.7 - TRAC-BWR Component Models", GEAP-22052, NUREG/CR-2574, EPRI NP-2376, April 1983.
    • (1983) NUREG/CR-2574
    • Cheung, Y.K.1    Parameswaran, V.2    Shaug, J.C.3
  • 14
    • 33845783744 scopus 로고
    • BWR full integral simulation test (FIST) program, TRAC-BWR model development, volume 1 - Numerical methods
    • GEAP-30875-1, EPRI NP-3987-1, November
    • J. G. M. Andersen and C. L. Heck, " BWR Full Integral Simulation Test (FIST) Program, TRAC-BWR Model Development, Volume 1 - Numerical Methods", GEAP-30875-1, NUREG/CR-4127-1, EPRI NP-3987-1, November 1985.
    • (1985) NUREG/CR-4127-1
    • Andersen, J.G.M.1    Heck, C.L.2
  • 15
    • 33845778889 scopus 로고
    • BWR full integral simulation test (FIST) program, TRAC-BWR model development, volume 2 - models
    • GEAP-30875-2, EPRI NP-3987-2, October
    • K. H. Chu, J. G. M. Andersen, Y. K. Cheung and J. C. Shaug, " BWR Full Integral Simulation Test (FIST) Program, TRAC-BWR Model Development, Volume 2 - Models", GEAP-30875-2, NUREG/CR-4127-2, EPRI NP-3987-2, October 1985.
    • (1985) NUREG/CR-4127-2
    • Chu, K.H.1    Andersen, J.G.M.2    Cheung, Y.K.3    Shaug, J.C.4
  • 16
    • 33845800201 scopus 로고
    • BWR REFILL/REFLOOD program task 4.8 - TRAC-BWR model qualification for BWR safety analysis, final report
    • GEAP-30157, EPRI NP-2377, October
    • Md. Alamgir, " BWR REFILL/REFLOOD Program Task 4.8 - TRAC-BWR Model Qualification for BWR Safety Analysis, Final Report", GEAP-30157, NUREG/CR-2571, EPRI NP-2377, October 1983.
    • (1983) NUREG/CR-2571
    • Alamgir, Md.1
  • 17
    • 33845778396 scopus 로고
    • BWR full integral simulation test (FIST) program, phase II test results and TRAC-BWR model qualification
    • GEAP-30876, EPRI NP-3988, October
    • W. A. Sutherland, Md. Alamgir J. A. Findlay and W. S. Hwang, " BWR Full Integral Simulation Test (FIST) Program, Phase II Test Results and TRAC-BWR Model Qualification", GEAP-30876, NUREG/CR-4128, EPRI NP-3988, October 1985
    • (1985) NUREG/CR-4128
    • Sutherland, W.A.1    Alamgir, Md.2    Findlay, J.A.3    Hwang, W.S.4
  • 20
    • 33845729381 scopus 로고
    • Determination of importance of uncertainty parameters in code applications
    • Washington, D. C., November 13-17
    • H. Glaeser, E. Hofer, " Determination of Importance of Uncertainty Parameters in Code Applications", Transaction of the American Nuclear Society, Washington, D. C., November 13-17, 1994, p. 308-309.
    • (1994) Transaction of the American Nuclear Society , pp. 308-309
    • Glaeser, H.1    Hofer, E.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.