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Volumn 37, Issue 12, 2010, Pages 1674-1682

Core and sub-channel analysis of SCWR with mixed spectrum core

Author keywords

Core design; Mixed spectrum; Multi physics coupling; Multi scale analysis; Super critical water cooled reactor (SCWR)

Indexed keywords

CORE DESIGN; MIXED SPECTRUM; MULTI SCALE ANALYSIS; MULTI-PHYSICS; SUPER-CRITICAL;

EID: 77956864067     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.07.014     Document Type: Article
Times cited : (30)

References (15)
  • 1
    • 0022133771 scopus 로고
    • Neutron physics investigations for advanced pressurized water reactors
    • C.H.M. Broeders Neutron physics investigations for advanced pressurized water reactors Nuclear Technology 71 1985 96
    • (1985) Nuclear Technology , vol.71 , pp. 96
    • Broeders, C.H.M.1
  • 2
    • 68349103184 scopus 로고    scopus 로고
    • Local thermal-hydraulic behavior in tight 7-rod bundles
    • X. Cheng, and Y.Q. Yu Local thermal-hydraulic behavior in tight 7-rod bundles Nuclear Engineering and Design 239 10 2009 1944 1955
    • (2009) Nuclear Engineering and Design , vol.239 , Issue.10 , pp. 1944-1955
    • Cheng, X.1    Yu, Y.Q.2
  • 3
    • 33846095101 scopus 로고    scopus 로고
    • Numerical analysis of heat transfer in supercritical water cooled flow channels
    • X. Cheng, B. Kuang, and Y.H. Yang Numerical analysis of heat transfer in supercritical water cooled flow channels Nuclear Engineering and Design 237 3 2007 240 252
    • (2007) Nuclear Engineering and Design , vol.237 , Issue.3 , pp. 240-252
    • Cheng, X.1    Kuang, B.2    Yang, Y.H.3
  • 5
    • 68149181757 scopus 로고    scopus 로고
    • Core and sub-channel evaluation of a thermal SCWR
    • X.J. Liu, and X. Cheng Core and sub-channel evaluation of a thermal SCWR Nuclear Engineering and Technology 41 5 2009 677 690
    • (2009) Nuclear Engineering and Technology , vol.41 , Issue.5 , pp. 677-690
    • Liu, X.J.1    Cheng, X.2
  • 6
    • 58149133576 scopus 로고    scopus 로고
    • Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly
    • X.J. Liu, and X. Cheng Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly Annals of Nuclear Energy 36 1 2009 28 36
    • (2009) Annals of Nuclear Energy , vol.36 , Issue.1 , pp. 28-36
    • Liu, X.J.1    Cheng, X.2
  • 8
    • 0035713218 scopus 로고    scopus 로고
    • Supercritical-pressure, once-through cycle light water cooled reactor concept
    • Y. Oka, and S. Koshizuka Supercritical-pressure, once-through cycle light water cooled reactor concept Journal of Nuclear Science and Technology 38 12 2001 1081 1089 (Pubitemid 34140726)
    • (2001) Journal of Nuclear Science and Technology , vol.38 , Issue.12 , pp. 1081-1089
    • Oka, Y.1    Koshizuka, S.2
  • 9
    • 39549106245 scopus 로고    scopus 로고
    • Three pass core design proposal for a high performance light water reactor
    • T. Schulenberg, J. Starflinger, and J. Heinecke Three pass core design proposal for a high performance light water reactor Progress in Nuclear Energy 50 2 2008 526 531
    • (2008) Progress in Nuclear Energy , vol.50 , Issue.2 , pp. 526-531
    • Schulenberg, T.1    Starflinger, J.2    Heinecke, J.3
  • 11
    • 16244380834 scopus 로고    scopus 로고
    • Improved core design of the high temperature supercritical-pressure light water reactor
    • A. Yamaji, K. Kamei, and Y. Oka Improved core design of the high temperature supercritical-pressure light water reactor Annals of Nuclear Energy 32 7 2005 651 670
    • (2005) Annals of Nuclear Energy , vol.32 , Issue.7 , pp. 651-670
    • Yamaji, A.1    Kamei, K.2    Oka, Y.3
  • 12
    • 33746061987 scopus 로고    scopus 로고
    • Evaluation of the nominal peak cladding surface temperature of the super LWR with subchannel analyses
    • Tsukuba, Japan, October 9-13 2005
    • Yamaji, A., Tanabe, T., Oka, Y., et al., 2005b. Evaluation of the nominal peak cladding surface temperature of the super LWR with subchannel analyses. In: Proceedings of GLOBAL 2005, Tsukuba, Japan, October 9-13, 2005.
    • (2005) Proceedings of GLOBAL 2005
    • Yamaji, A.1    Tanabe, T.2    Oka, Y.3
  • 13
    • 33846460766 scopus 로고    scopus 로고
    • Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles
    • J. Yang, Y. Oka, and Y. Ishiwatari Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles Nuclear Engineering and Design 237 4 2007 420 430
    • (2007) Nuclear Engineering and Design , vol.237 , Issue.4 , pp. 420-430
    • Yang, J.1    Oka, Y.2    Ishiwatari, Y.3
  • 15
    • 33747882212 scopus 로고    scopus 로고
    • Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling
    • J. Yoo, Y. Ishiwatari, and Y. Oka Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling Annals of Nuclear Energy 33 11-12 2006 945 956
    • (2006) Annals of Nuclear Energy , vol.33 , Issue.11-12 , pp. 945-956
    • Yoo, J.1    Ishiwatari, Y.2    Oka, Y.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.