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Volumn 48, Issue 6, 2006, Pages 559-568

Thermal hydraulic analysis of the thorium-based advanced CANDU Reactor fuel channel

Author keywords

Onset of dry out power; Subchannel; Thermal hydraulic; Thorium based

Indexed keywords

BOUNDARY CONDITIONS; NUCLEAR FUELS; THORIUM; URANIUM;

EID: 33746918366     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2006.02.002     Document Type: Article
Times cited : (6)

References (6)
  • 1
    • 33746912947 scopus 로고    scopus 로고
    • Beuthe, T.G., Hanna, B.N., Nov. 2004. CATHENA MOD-3.5d/Rev 1 Input Reference. Atomic Energy of Canada Limited. 87-03500-400-001. Revision 1.
  • 3
    • 0029513589 scopus 로고
    • Validation of the ASSERT subchannel code: prediction of critical heat flux in standard and nonstandard CANDU bundle geometries
    • Carver M.B., Kiteley J.C., Zhou R.Q.-N., and Junop S.V. Validation of the ASSERT subchannel code: prediction of critical heat flux in standard and nonstandard CANDU bundle geometries. Nuclear Technology 112 3 (Dec. 1995) 299-314
    • (1995) Nuclear Technology , vol.112 , Issue.3 , pp. 299-314
    • Carver, M.B.1    Kiteley, J.C.2    Zhou, R.Q.-N.3    Junop, S.V.4
  • 4
    • 33746905324 scopus 로고    scopus 로고
    • Hedges, Ken. The Advanced CANDU Reactor (ACR): ready for the emerging market. ANES 2002 Symposium, October 16-18, 2002.
  • 6
    • 33746897190 scopus 로고    scopus 로고
    • Rao, Y.F., Mar. 2004. ASSERT-PV V3R1 IST User's Manual. Industry Standard Toolset Document, AECL Host Organization, RSD-TH-007/RC-2913. Revision 0.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.