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Volumn , Issue , 2003, Pages 2182-2187

Benchmark of dynamic simulation tools for molten salt reactors

Author keywords

[No Author keywords available]

Indexed keywords

APPROXIMATION THEORY; COMPUTATIONAL METHODS; COMPUTER SIMULATION; DYNAMIC RESPONSE; FEEDBACK; GRAPHITE; NEUTRONS; NUCLEAR FUELS;

EID: 2642530319     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (37)

References (11)
  • 4
    • 0037263129 scopus 로고    scopus 로고
    • A neutronic program for critical and nonequilibrium study of mobile reactors: The cinsf1D code
    • D. LECARPENTIER, V. CARPENTIER, "A Neutronic Program for Critical and Nonequilibrium Study of Mobile Reactors: the Cinsf1D Code", Nuclear Science and Engineering, 143, 2003.
    • (2003) Nuclear Science and Engineering , vol.143
    • Lecarpentier, D.1    Carpentier, V.2
  • 6
    • 0004276478 scopus 로고    scopus 로고
    • Effective delayed neutron fraction for fluid-fuel systems
    • F. MATTIODA, P. RAVETTO, G. RITTER, "Effective Delayed Neutron Fraction for Fluid-Fuel Systems", Annals of Nuclear Energy, 27, 1523-1532, 2000.
    • (2000) Annals of Nuclear Energy , vol.27 , pp. 1523-1532
    • Mattioda, F.1    Ravetto, P.2    Ritter, G.3
  • 7
    • 0000248886 scopus 로고
    • SIMMER-III: An advanced computer program for LMFBR severe accident analysis
    • Tokyo
    • S. KONDO, K. MORITA, Y. TOBITA, N. SHIRAKAWA, "SIMMER-III: an Advanced Computer Program for LMFBR Severe Accident Analysis", ANP'92, Tokyo, 1992.
    • (1992) ANP'92
    • Kondo, S.1    Morita, K.2    Tobita, Y.3    Shirakawa, N.4
  • 8
    • 0035575480 scopus 로고    scopus 로고
    • Assessment of the kinetic and dynamic transient behavior of sub-critical systems (ADS) in comparison to critical reactor systems
    • W.M. SCHIKORR, "Assessment of the Kinetic and Dynamic Transient Behavior of Sub-Critical Systems (ADS) in Comparison to Critical Reactor Systems", Nuclear Engineering and Design, 210, 95-123, 2001.
    • (2001) Nuclear Engineering and Design , vol.210 , pp. 95-123
    • Schikorr, W.M.1
  • 9
    • 2642554357 scopus 로고    scopus 로고
    • Development and verification of a reactor dynamics code for molten salt reactors with flowing fuel
    • Berlin, 20-22 May
    • J. KREPEL, U. GRUNDMANN, U. ROHDE, "Development and Verification of a Reactor Dynamics Code for Molten Salt Reactors with Flowing Fuel", Proceedings of the Annual Meeting on Nuclear Technology, Berlin, 20-22 May, 2003.
    • (2003) Proceedings of the Annual Meeting on Nuclear Technology
    • Krepel, J.1    Grundmann, U.2    Rohde, U.3
  • 10
    • 0348164716 scopus 로고    scopus 로고
    • Quasi-static method for the time-dependent neutronics of fluid-fuel systems
    • New Orleans, 16-20 November
    • S. DULLA, M.M. ROSTAGNO, P. RAVETTO, "Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems", American Nuclear Society Winter Meeting, New Orleans, 16-20 November, 2003.
    • (2003) American Nuclear Society Winter Meeting
    • Dulla, S.1    Rostagno, M.M.2    Ravetto, P.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.