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Volumn 392, Issue 1, 2009, Pages 6-15

Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods

Author keywords

[No Author keywords available]

Indexed keywords

ANALYSIS CAPABILITIES; CLADDING BARRIERS; COUPLED SIMULATION; EQUATION SYSTEMS; FISSILE MATERIALS; FUEL PELLETS; FUEL PERFORMANCE; FULLY-COUPLED; JACOBIANS; NEWTON KRYLOV METHOD; NUCLEAR FUEL ROD; NUMERICAL RESULTS; OXYGEN DIFFUSION; PERFORMANCE CODE; REACTOR FUELS; STEADY STATE; THERMO-MECHANICS; THERMOMECHANICAL MODEL; THERMOMECHANICAL PROCESS; THREE-DIMENSIONAL MODEL;

EID: 67349102262     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2009.03.035     Document Type: Article
Times cited : (85)

References (30)
  • 20
    • 67349095530 scopus 로고    scopus 로고
    • J.K. Hohorst, SCDAP/RELAP5/MOD2 Code Manual, 4: MATPRO-A Library of Materials Properties for Light-Water-Reactor Accident Analysis, Technical Report, NUREG/CR-5273, EGG-2555, 1990.
    • J.K. Hohorst, SCDAP/RELAP5/MOD2 Code Manual, Volume. 4: MATPRO-A Library of Materials Properties for Light-Water-Reactor Accident Analysis, Technical Report, NUREG/CR-5273, EGG-2555, 1990.
  • 22
    • 34447624737 scopus 로고
    • PWS Publishing Company, Boston, MA
    • Saad Y. Iterative Methods for Sparse Linear Systems. The PWS Series in Computer Science (1995), PWS Publishing Company, Boston, MA
    • (1995) The PWS Series in Computer Science
    • Saad, Y.1
  • 28
    • 67349150993 scopus 로고    scopus 로고
    • McInnes, Barry F. Smith, Hong Zhang, PETSc Users Manual
    • Technical Report ANL-95/11, Revision 2.1.5, Argonne National Laboratory
    • Satish Balay, Kris Buschelman, Victor Eijkhout, William D. Gropp, Dinesh Kaushik, Matthew G. Knepley, Lois Curfman McInnes, Barry F. Smith, Hong Zhang, PETSc Users Manual, Technical Report ANL-95/11 - Revision 2.1.5, Argonne National Laboratory, 2004.
    • (2004)
    • Balay, S.1    Buschelman, K.2    Eijkhout, V.3    Gropp, W.D.4    Kaushik, D.5    Knepley, M.G.6    Curfman, L.7
  • 30
    • 80053171484 scopus 로고    scopus 로고
    • M.A. Pope, V.A. Mousseau, in: The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Log Number: 239, Sheraton Station Square, Pittsburgh, Pennsylvania, USA., 2007.
    • M.A. Pope, V.A. Mousseau, in: The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Log Number: 239, Sheraton Station Square, Pittsburgh, Pennsylvania, USA., 2007.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.