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Volumn 2006, Issue , 2006, Pages

Transient accident analysis of a supercritical carbon dioxide brayton cycle energy converter coupled to an autonomous lead-cooled fast reactor

Author keywords

[No Author keywords available]

Indexed keywords

ENERGY CONVERTERS; NATURAL CIRCULATION; SATURATED STEAM CYCLE;

EID: 33845809490     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE14-89544     Document Type: Conference Paper
Times cited : (7)

References (6)
  • 2
    • 34249098419 scopus 로고    scopus 로고
    • SSTAR lead-cool, small modular fast reactor for deployment at remote sites - System thermal hydraulic development
    • Seoul, May 15-19, Paper 5426
    • J. J. SIENICKI and A. V. MOISSEYTSEV, "SSTAR Lead-Cool, Small Modular Fast Reactor for Deployment at Remote Sites - System Thermal Hydraulic Development," 2005 International Congress on Advances in Nuclear Power Plants (ICAPP 2005), Seoul, May 15-19, 2005, Paper 5426.
    • (2005) 2005 International Congress on Advances in Nuclear Power Plants (ICAPP 2005)
    • Sienicki, J.J.1    Moisseytsev, A.V.2
  • 3
    • 4344609403 scopus 로고    scopus 로고
    • Safety and licensing aspects of the LFR/SSTAR
    • Pittsburgh, June 13-17. 2004, Transactions of the American Nuclear Society
    • J. J. SIENICKI, "Safety and Licensing Aspects of the LFR/SSTAR," American Nuclear Society 2004 Annual Meeting, Pittsburgh, June 13-17. 2004, Transactions of the American Nuclear Society, Vol. 90, p. 24, 2004.
    • (2004) American Nuclear Society 2004 Annual Meeting , vol.90 , pp. 24
    • Sienicki, J.J.1
  • 6
    • 0008908298 scopus 로고
    • Advanced LMR safety analysis capabilities in the SASSYS-1 and SAS4A computer codes
    • Pittsburgh, April 17-21, American Nuclear Society, La Grange Park (1994)
    • J. E. CAHALAN, A. M. TENTNER, and E. E. MORRIS, "Advanced LMR Safety Analysis Capabilities in the SASSYS-1 and SAS4A Computer Codes," Proceedings of the International Topical Meeting on Advanced Reactor Safety, Pittsburgh, April 17-21, 1994, Vol. 2, p. 1038, American Nuclear Society, La Grange Park (1994).
    • (1994) Proceedings of the International Topical Meeting on Advanced Reactor Safety , vol.2 , pp. 1038
    • Cahalan, J.E.1    Tentner, A.M.2    Morris, E.E.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.