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Volumn , Issue , 2003, Pages

Assessment of the Emergency Core Cooling System (ECCS) performance for current and advanced plant designs using WCOBRA/TRAC

Author keywords

[No Author keywords available]

Indexed keywords

CODES (SYMBOLS); COOLING SYSTEMS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; PRESSURIZED WATER REACTORS; REACTOR CORES; THERMOELECTRIC EQUIPMENT; TWO PHASE FLOW; UNCERTAINTY ANALYSIS;

EID: 84933180360     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (6)

References (13)
  • 1
    • 0346332422 scopus 로고
    • Code qualification document for best-estimate LOCA analysis
    • S.M. Bajorek, "Code Qualification Document for Best-Estimate LOCA Analysis" WCAP-12945 (1992).
    • (1992) WCAP-12945
    • Bajorek, S.M.1
  • 2
    • 0010695798 scopus 로고
    • COBRA/TRAC - A thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems
    • M. J. Thurgood et al, "COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems," NUREG/CR-3046 (1983)
    • (1983) NUREG/CR-3046
    • Thurgood, M.J.1
  • 4
    • 0343059282 scopus 로고
    • TRAC-PD2, an advanced best-estimate computer program for pressurized water reactor loss-of-coolant accident analysis
    • D.R. Liles et al., "TRAC-PD2, An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Loss-of-Coolant Accident Analysis," NUREG/CR-2054. (1981)
    • (1981) NUREG/CR-2054
    • Liles, D.R.1
  • 5
    • 84880457436 scopus 로고
    • Analysis of FLECHT-SEASET 163 rod bundle data using COBRA-TF
    • C.Y. Paik and L.E. Hochreiter, "Analysis of FLECHT-SEASET 163 Rod Bundle Data Using COBRA-TF," NUREG/CR-4166 (1986).
    • (1986) NUREG/CR-4166
    • Paik, C.Y.1    Hochreiter, L.E.2
  • 6
    • 0012482956 scopus 로고
    • Quantifying reactor safety margins: Application of code scaling, applicability, and uncertainty evaluation methodology to large break, loss-of-coolant accident
    • B. Boyack et al., "Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to Large Break, Loss-of-Coolant Accident," NUREG/CR-5249. (1989).
    • (1989) NUREG/CR-5249
    • Boyack, B.1
  • 8
    • 0343345570 scopus 로고
    • User effects on the thermal-hydraulic transient system code calculations
    • S. N. Aksan, F. D'Auria and H. Stadtke, "User effects on the thermal-hydraulic transient system code calculations," Nucl. Engineering and Design, 145, 159-174 (1993).
    • (1993) Nucl. Engineering and Design , vol.145 , pp. 159-174
    • Aksan, S.N.1    D'Auria, F.2    Stadtke, H.3
  • 10
    • 0032206536 scopus 로고    scopus 로고
    • Application of the WCOBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis
    • J. Zhang, S. M. Bajorek, R. M. Kemper, M. E. Nissley, N. Petkov, and L. E. Hochreiter, "Application of the WCOBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 279-301.
    • (1998) Nuclear Engineering and Design , vol.186 , Issue.1-2 , pp. 279-301
    • Zhang, J.1    Bajorek, S.M.2    Kemper, R.M.3    Nissley, M.E.4    Petkov, N.5    Hochreiter, L.E.6
  • 12
    • 0346307940 scopus 로고    scopus 로고
    • Assessment of flooding in a best-estimate thermal hydraulic code (WCOBRA/TRAC)
    • K. Takeuchi, and M. Y. Young, "Assessment of flooding in a best-estimate thermal hydraulic code (WCOBRA/TRAC)," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 225-255.
    • (1998) Nuclear Engineering and Design , vol.186 , Issue.1-2 , pp. 225-255
    • Takeuchi, K.1    Young, M.Y.2
  • 13
    • 0347568942 scopus 로고    scopus 로고
    • Scaling effects predicted by WCOBRA/TRAC for UPI plant best estimate LOCA
    • K. Takeuchi, M. E. Nissley, J. S. Spaargaren, and S. I. Dederer, "Scaling effects predicted by WCOBRA/TRAC for UPI plant best estimate LOCA," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 257-278.
    • (1998) Nuclear Engineering and Design , vol.186 , Issue.1-2 , pp. 257-278
    • Takeuchi, K.1    Nissley, M.E.2    Spaargaren, J.S.3    Dederer, S.I.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.