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Volumn 239, Issue 8, 2009, Pages 1425-1441

Neutronic analysis of hydride fueled PWR cores

Author keywords

[No Author keywords available]

Indexed keywords

ASSEMBLY CALCULATION; BORON CONCENTRATIONS; BURN UP; BURNABLE POISONS; COOLANT TEMPERATURE; DESIGN SPACES; DISCHARGE BURN-UP; ENRICHED URANIUM; FUEL RODS; FUEL TEMPERATURE; HYDRIDE FUEL; NEUTRONIC; NEUTRONIC ANALYSIS; NON-LINEAR; OUTER DIAMETERS; OXIDE FUELS; PARAMETRIC STUDY; REACTIVITY COEFFICIENTS; SIMPLIFIED PROCEDURE; THORIUM HYDRIDE; UNIT CELLS; VOID REACTIVITY COEFFICIENT;

EID: 67349164280     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.12.027     Document Type: Article
Times cited : (13)

References (17)
  • 1
    • 0003662791 scopus 로고
    • A User's Manual for the ORIGEN2 Computer Code
    • ORNL/TM-7175
    • Croff, A.G., 1980. A User's Manual for the ORIGEN2 Computer Code, Oak Ridge National Laboratory Report. ORNL/TM-7175.
    • (1980) Oak Ridge National Laboratory Report
    • Croff, A.G.1
  • 2
    • 67349176935 scopus 로고    scopus 로고
    • TRITON: A Two Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
    • Oak Ridge National Laboratory
    • DeHart, M.D., 2005a. TRITON: A Two Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel. Nuclear science and technology division (94), Oak Ridge National Laboratory.
    • (2005) Nuclear science and technology division
    • DeHart, M.D.1
  • 3
    • 67349272755 scopus 로고    scopus 로고
    • NEWT: A New Transport Algorithm for Two-Dimensional Discrete Ordinates Analysis in Non-Orthogonal Geometries
    • Oak Ridge National Laboratory
    • DeHart, M.D., 2005b. NEWT: A New Transport Algorithm for Two-Dimensional Discrete Ordinates Analysis in Non-Orthogonal Geometries. Nuclear science and technology division (94), Oak Ridge National Laboratory.
    • (2005) Nuclear science and technology division
    • DeHart, M.D.1
  • 4
    • 67349271474 scopus 로고    scopus 로고
    • Fratoni, M., Ginex, F., Ganda, F., Greenspan, E., Handwerk, C., Ferroni, P., Todreas, N., 2006. Feasibility of Improving BWR Performance Using Hydride Fuel. ICAPP-2006, Reno, NV.
    • Fratoni, M., Ginex, F., Ganda, F., Greenspan, E., Handwerk, C., Ferroni, P., Todreas, N., 2006. Feasibility of Improving BWR Performance Using Hydride Fuel. ICAPP-2006, Reno, NV.
  • 6
    • 67349104072 scopus 로고    scopus 로고
    • A simplified method for multi-batch PWR core analysis based on SAS2H unit cell calculations
    • Avignon, France
    • Ganda F., and Greenspan E. A simplified method for multi-batch PWR core analysis based on SAS2H unit cell calculations. Proc. Int. Mtg. Mathematics and Computation-MC2005. Avignon, France (2005)
    • (2005) Proc. Int. Mtg. Mathematics and Computation-MC2005
    • Ganda, F.1    Greenspan, E.2
  • 10
    • 67349233492 scopus 로고    scopus 로고
    • Hydride fuel for LWRs-Project overview
    • Greenspan E., et al. Hydride fuel for LWRs-Project overview. Nuclear Engineering and Design 239 (2009) 1374-1405
    • (2009) Nuclear Engineering and Design , vol.239 , pp. 1374-1405
    • Greenspan, E.1
  • 12
    • 67349216528 scopus 로고    scopus 로고
    • Hermann, O.W., Parks, C.V., 1998. SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module. NUREG-CR-0200, Rev. 6, 1, Section 2. Oak Ridge National Laboratory.
    • Hermann, O.W., Parks, C.V., 1998. SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module. NUREG-CR-0200, Rev. 6, vol. 1, Section 2. Oak Ridge National Laboratory.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.