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Volumn , Issue , 2007, Pages 872-884

Transient thermal response of the PB-AHTR to loss of forced cooling

Author keywords

[No Author keywords available]

Indexed keywords

3-D SIMULATIONS; DECAY HEAT REMOVAL (DHR); FORCED COOLING; HIGH TEMPERATURE (HT); MODULAR HELIUM REACTORS (MHR); NATURAL CIRCULATION; NUCLEAR-FUEL CYCLES; PEBBLE BEDS; POWER DENSITY (PD); TEMPERATURE DIFFERENCES; TRANSIENT THERMAL RESPONSE;

EID: 45149121746     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (11)

References (13)
  • 2
    • 45149126427 scopus 로고    scopus 로고
    • The Pebble Recirculation Experiment (PREX) for the AHTR
    • P. BARDET et al., "The Pebble Recirculation Experiment (PREX) for the AHTR," this conference.
    • this conference
    • BARDET, P.1
  • 3
    • 45149085002 scopus 로고    scopus 로고
    • A. GRIVEAU, Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), M.S. Project Report, UCBTH-07-001, UC Berkeley (March 2007).
    • A. GRIVEAU, "Modeling and Transient Analysis for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR)," M.S. Project Report, UCBTH-07-001, UC Berkeley (March 2007).
  • 6
    • 85136088138 scopus 로고
    • Combined forced and free laminar transfer in vertical tubes with uniform internal heat generation
    • T.M. HALLMAN, "Combined forced and free laminar transfer in vertical tubes with uniform internal heat generation", Trans. ASME 77, 1831 (1956)
    • (1956) Trans. ASME , vol.77 , pp. 1831
    • HALLMAN, T.M.1
  • 7
    • 45149131167 scopus 로고    scopus 로고
    • RELAP5-3D© Code Manual Volume IV: Models and Correlations
    • "RELAP5-3D© Code Manual Volume IV: Models and Correlations", INEEL-EXT-98-00834 (2005)
    • INEEL-EXT-98-00834 (2005)
  • 9
    • 45149095361 scopus 로고    scopus 로고
    • Design of Scaled Integral Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Heat Transfer
    • Avignon, France, October 2-6
    • P. BARDET and P.F. PETERSON, "Design of Scaled Integral Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Heat Transfer", in Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Avignon, France, October 2-6 2005
    • (2005) Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics
    • BARDET, P.1    PETERSON, P.F.2
  • 12
    • 45149097125 scopus 로고    scopus 로고
    • Neutronic and Depletion Analysis of the PB-AHTR
    • M. FRATONI et al., "Neutronic and Depletion Analysis of the PB-AHTR", this conference
    • this conference
    • FRATONI, M.1
  • 13
    • 2642549518 scopus 로고    scopus 로고
    • Idaho National Engineering and Environmental Laboratory (September 2003), INEEL/EXT-03-00870 Rev. 1
    • P.E. MACDONALD, et. al., "NGNP Preliminary Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments", Idaho National Engineering and Environmental Laboratory (September 2003), INEEL/EXT-03-00870 Rev. 1.
    • MACDONALD, P.E.1    et., al.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.