메뉴 건너뛰기




Volumn 34, Issue 6, 2007, Pages 501-513

Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis

Author keywords

[No Author keywords available]

Indexed keywords

ALGORITHMS; CODES (STANDARDS); NEUTRON FLUX; NUCLEAR REACTOR ACCIDENTS; PARALLEL PROCESSING SYSTEMS; REACTOR CORES; TRANSIENT ANALYSIS;

EID: 34248598929     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.02.016     Document Type: Article
Times cited : (98)

References (16)
  • 1
    • 34248559701 scopus 로고    scopus 로고
    • Allison, C. et al., 1990. RELAP5/MOD3 code manual. NUREG/CR-5535.
  • 2
    • 33847202213 scopus 로고    scopus 로고
    • Avramova, M., Ivanov, K., Cuervo, D., 2006. Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses. In: Proceedings of PHYSOR-2006 Conference, CD-Rom (Electronic Publication), Vancouver, Canada.
  • 3
    • 34248551759 scopus 로고    scopus 로고
    • Borkowski, J. et al., 1992. TRAC-BF1: an advanced best-estimate computer program for BWR accident analysis. NUREG/CR-4356.
  • 4
    • 34248520717 scopus 로고    scopus 로고
    • Dias, A. 1997. CORETRAN-01 - theory and numerical analysis. EPRI.
  • 5
    • 33847231861 scopus 로고    scopus 로고
    • Hu, Y., Downar, T., Kozlowski, T., Ivanov, K., Staudenmeier, J., 2006. Multi-physics coupled code reactor analysis with the US NRC code system TRACE/PARCS. In: Proceedings of PHYSOR-2006 Conference, CD-Rom (Electronic Publication), Vancouver, Canada.
  • 6
    • 34248536391 scopus 로고    scopus 로고
    • Ivanov, K., Baratta, A., 1999. Coupling methodologies for best estimate safety analysis. In: Proceedings of M&C'99 Conference, vol. 1, Madrid, Spain, pp. 493-502.
  • 7
    • 0038754027 scopus 로고    scopus 로고
    • Using the OECD/NRC PWR MSLB benchmark to study current numerical and computational issues of coupled calculations
    • Ivanov K., Todorova N., and Sartori E. Using the OECD/NRC PWR MSLB benchmark to study current numerical and computational issues of coupled calculations. Nuclear Technology 142 2 (2003) 95-115
    • (2003) Nuclear Technology , vol.142 , Issue.2 , pp. 95-115
    • Ivanov, K.1    Todorova, N.2    Sartori, E.3
  • 8
    • 9144272725 scopus 로고    scopus 로고
    • OECD/NRC BWR TT benchmark as a basis for comprehensive qualification and studying best estimate coupled codes
    • Ivanov K., Olson A., and Sartori E. OECD/NRC BWR TT benchmark as a basis for comprehensive qualification and studying best estimate coupled codes. Nuclear Science and Engineering 148 2 (2004) 195-207
    • (2004) Nuclear Science and Engineering , vol.148 , Issue.2 , pp. 195-207
    • Ivanov, K.1    Olson, A.2    Sartori, E.3
  • 9
    • 33846949379 scopus 로고    scopus 로고
    • Validation of coupled thermal-hydraulic and neutronics codes for safety analysis by international co-operations
    • Ivanov K., Sartori E., Royer E., Langenbuch S., and Velkov K. Validation of coupled thermal-hydraulic and neutronics codes for safety analysis by international co-operations. Nuclear Technology 157 2 (2007) 177-195
    • (2007) Nuclear Technology , vol.157 , Issue.2 , pp. 177-195
    • Ivanov, K.1    Sartori, E.2    Royer, E.3    Langenbuch, S.4    Velkov, K.5
  • 10
    • 34248567941 scopus 로고    scopus 로고
    • Schnurr, N. et al., 1992. TRAC-PF1/MOD2 code manual. NUREG/CR-5673, LA-12031-M. vol. 2.
  • 11
    • 0036885233 scopus 로고    scopus 로고
    • Temporal adaptive algorithm for TRAC-BF1/NEM/COBRA-TF coupled calculations in BWR safety analysis
    • Solis J., Avramova M., and Ivanov K. Temporal adaptive algorithm for TRAC-BF1/NEM/COBRA-TF coupled calculations in BWR safety analysis. Annals of Nuclear Energy 29 (2002) 2127-2141
    • (2002) Annals of Nuclear Energy , vol.29 , pp. 2127-2141
    • Solis, J.1    Avramova, M.2    Ivanov, K.3
  • 12
    • 3142772618 scopus 로고    scopus 로고
    • Multi-level methodology in parallel computing environment for evaluating BWR safety parameters
    • Solis J., Avramova M., and Ivanov K. Multi-level methodology in parallel computing environment for evaluating BWR safety parameters. Nuclear Technology 146 3 (2004) 267-278
    • (2004) Nuclear Technology , vol.146 , Issue.3 , pp. 267-278
    • Solis, J.1    Avramova, M.2    Ivanov, K.3
  • 13
    • 34248522647 scopus 로고    scopus 로고
    • Thurgood, M. et al., 1983. COBRA/TRAC - a thermal-hydraulic code for transient analysis of nuclear reactor vessel and primary coolant systems. NUREG/CR-3046.
  • 14
    • 34248504717 scopus 로고    scopus 로고
    • Todorova, N., Ivanov, K., 2001. PWR REA sensitivity analysis using TRAC-PF1/NEM. In: Proceedings of ICONE-9 Conference, CD-Rom (Electronic Publication), Nice, France.
  • 15
    • 0036568015 scopus 로고    scopus 로고
    • Improved cross-section modeling methodology for coupled three-dimensional transient calculations
    • Watson J., and Ivanov K. Improved cross-section modeling methodology for coupled three-dimensional transient calculations. Annals of Nuclear Energy 29 (2002) 937-966
    • (2002) Annals of Nuclear Energy , vol.29 , pp. 937-966
    • Watson, J.1    Ivanov, K.2
  • 16
    • 9944239882 scopus 로고    scopus 로고
    • Development of PWR integrated safety analysis methodology using multi-level coupling algorithm
    • Ziabletsev D., Avramova M., and Ivanov K. Development of PWR integrated safety analysis methodology using multi-level coupling algorithm. Nuclear Science and Engineering 148 3 (2004) 414-425
    • (2004) Nuclear Science and Engineering , vol.148 , Issue.3 , pp. 414-425
    • Ziabletsev, D.1    Avramova, M.2    Ivanov, K.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.