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Volumn 47, Issue , 2012, Pages 6-13

Burnup span sensitivity analysis of different burnup coupling schemes

Author keywords

Burnup span; Monte Carlo depletion; Predictor corrector; Sensitivity analysis; Transition matrix

Indexed keywords

ABSOLUTE DIFFERENCE; BURN UP; BURN-UP EFFECT; BURNUP CALCULATION; CASMO-4; CODE COMPARISONS; CORE COMPOSITION; COUPLING SCHEME; COUPLING TECHNIQUES; CROSS SECTION; EIGEN-VALUE; EULER METHOD; FIRST ORDER; FIRST ORDER METHOD; HIGH-BURN UP; ISOTOPIC COMPOSITION; MONTE CARLO; NEUTRON FLUX DISTRIBUTIONS; NONLINEAR BEHAVIOR; PREDICTOR CORRECTOR; SECOND ORDERS; SECOND-ORDER SCHEME; SPATIAL VARIATIONS; STATE OF THE ART; TIME STEP; TRANSITION MATRICES; TRANSPORT METHOD;

EID: 84860697500     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2012.04.010     Document Type: Article
Times cited : (10)

References (15)
  • 1
    • 78751610999 scopus 로고    scopus 로고
    • Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method
    • A. Acir, H. Coskun, H.M. Sahin, and O. Erol Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method Ann. Nucl. Energy 38 2011 298 301
    • (2011) Ann. Nucl. Energy , vol.38 , pp. 298-301
    • Acir, A.1    Coskun, H.2    Sahin, H.M.3    Erol, O.4
  • 2
    • 76849083360 scopus 로고    scopus 로고
    • Comparison among MCNP-based depletion codes applied to burn up calculations of pebble-bed HTR lattices
    • E. Bomboni, N. Cerullo, E. Fridman, G. Lomonaco, and E. Shwageraus Comparison among MCNP-based depletion codes applied to burn up calculations of pebble-bed HTR lattices Nucl. Eng. Des. 240 2010 918 924
    • (2010) Nucl. Eng. Des. , vol.240 , pp. 918-924
    • Bomboni, E.1    Cerullo, N.2    Fridman, E.3    Lomonaco, G.4    Shwageraus, E.5
  • 3
    • 0347128560 scopus 로고    scopus 로고
    • Comparison between HELIOS critical-depletion calculations and a PWR thorium cell burn up benchmark
    • A.N. Carrera, J.L. Francois, and G.E. Paredes Comparison between HELIOS critical-depletion calculations and a PWR thorium cell burn up benchmark Ann. Nucl. Energy 31 2004 713 722
    • (2004) Ann. Nucl. Energy , vol.31 , pp. 713-722
    • Carrera, A.N.1    Francois, J.L.2    Paredes, G.E.3
  • 6
    • 33845516942 scopus 로고    scopus 로고
    • Incorporation of a Predictor-Corrector Methodology and 1-Group Reaction Rate Reporting Scheme for the MCNPX Depletion Capability
    • Los Alamos National Laboratory Report LA-UR-06-3925, Transactions of the American Nuclear Society Albuquerque, New Mexico
    • Fensin, M.L., Hendricks, J., Trellue, H., Anghaie, S., 2006. Incorporation of a Predictor-Corrector Methodology and 1-Group Reaction Rate Reporting Scheme for the MCNPX Depletion Capability., Los Alamos National Laboratory Report LA-UR-06-3925, Transactions of the American Nuclear Society, vol. 95, Winter Meeting, Albuquerque, New Mexico, p. 317.
    • (2006) Winter Meeting , vol.95 , pp. 317
    • Fensin, M.L.1    Hendricks, J.2    Trellue, H.3    Anghaie, S.4
  • 7
    • 79953873861 scopus 로고    scopus 로고
    • Implementation of multi-group cross - Section methodology in BGCore MC-depletion code
    • Interlaken, Switzerland
    • Fridman, E., Shwageraus, E., Galperin, A., 2008. Implementation of multi-group cross - section methodology in BGCore MC-depletion code. In: Proceeding of PHYSOR 2008, Interlaken, Switzerland.
    • (2008) Proceeding of PHYSOR 2008
    • Fridman, E.1    Shwageraus, E.2    Galperin, A.3
  • 8
    • 84862863984 scopus 로고    scopus 로고
    • Version 26E, Los Alamos National Laboratory, Report LA-UR-07-6632
    • Hendricks, J.S., et al., 2007. MCNPX, Version 26E, Los Alamos National Laboratory, Report LA-UR-07-6632.
    • (2007) MCNPX
    • Hendricks, J.S.1
  • 9
    • 77950298366 scopus 로고    scopus 로고
    • Xenon transient simulation of the VVER-1000 nuclear reactor using adiabatic approximation
    • M. Kheradmand saadi, M. Shahriari, and A.R. Zolfaghari Xenon transient simulation of the VVER-1000 nuclear reactor using adiabatic approximation Ann. Nucl. Energy 37 2010 753 761
    • (2010) Ann. Nucl. Energy , vol.37 , pp. 753-761
    • Kheradmand Saadi, M.1    Shahriari, M.2    Zolfaghari, A.R.3
  • 10
    • 0003486319 scopus 로고
    • INEL-95/0523, Idaho National Engineering Laboratory, September 1995
    • Moore, R.L., et al., 1995. MOCUP: MCNP-ORIGEN2 Coupled Utility Program, INEL-95/0523, Idaho National Engineering Laboratory, September 1995.
    • (1995) MOCUP: MCNP-ORIGEN2 Coupled Utility Program
    • Moore, R.L.1
  • 11
    • 78751607154 scopus 로고    scopus 로고
    • Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a gas-cooled fast reactor
    • R.R. Ramirez, C.M. Del-Campo, J.L. Francois, E. Brun, E. Dumonteil, and F. Malvagi Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a gas-cooled fast reactor Ann. Nucl. Energy 37 2010 1101 1106
    • (2010) Ann. Nucl. Energy , vol.37 , pp. 1101-1106
    • Ramirez, R.R.1    Del-Campo, C.M.2    Francois, J.L.3    Brun, E.4    Dumonteil, E.5    Malvagi, F.6


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.