연구동향 분석

Improvement and Verification of the DeCART code for HTGR Core Physics Analysis

조진영 한태영 박호진 홍서기 이현철 2019년

논문상세정보
인용/피인용
' Improvement and Verification of the DeCART code for HTGR Core Physics Analysis' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Adjoint solver
  • DeCART
  • Numerical benchmark
  • Two-level parallelization
  • htgr
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
24 0

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' Improvement and Verification of the DeCART code for HTGR Core Physics Analysis' 의 참고문헌

  • Whole core transport calculation employing hexagonal modular ray tracing and CMFD formulation
    J.Y. Cho [2008]
  • Uncertainty analysis with double heterogeneity treatment based on the generalized perturbation theory
    T. Y. Han [2017]
  • Two-level coarse mesh finite difference formulation with multigroup source expansion nodal kernels
    J. Il Yoon [2008]
  • Two-dimensional whole core transport calculations using paragon
  • Treatment of the double heterogeneity with the method of characteristics
    R. Sanchez [2002]
  • The NJOY Nuclear Data Processing System:Version 91
  • The Coupling of the STAR-CD software to a whole-core neutron transport code DeCART for PWR Applications
    J.W. Thomas [2003]
  • STAR-CD User Giude Version 3.26
  • Resolution of double heterogeneity in direct transport calculation employing subgroup method and method of characteristics
  • Renormalized treatment of the double heterogeneity with the method of characteristics
    R. Sanchez [2004]
  • Quadratic depletion method for gadolinium isotopes in CASMO-5
    D. Lee [2013]
  • Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
    Y. S. Jung [2013]
  • Parallelization of a three dimensional whole core transport code DeCART
    J.Y. Cho [2003]
  • Overview of development and design of MPACT: Michigan parallel characteristics transport code
    B. Kochunas [2013]
  • OECD/NEA Coupled Neutronic/Thermal-fluids Benchmark of the MHTGR-350 MW Core Design Volume III: Lattice Physics Exercises, Draft Date: 1/15/2015
  • OECD/NEA Coupled Neutronic/Thermal-fluids Benchmark of the MHTGR-350 MW Core Design Volume I: Reference Design Definition, Draft Date: 1/15/2015
  • Numerical solution of stiff burnup equation with short half lived nuclides by the krylov subspace method
    A. Yamamoto [2007]
  • Numerical benchmarks for very high-temperature reactors based on the CNPS critical experiments
    H. -K. Joo [2008]
  • Master-3.0: Multi-purpose Analyzer for Static and Transient Effects of Reactors
    B. O. Cho [2002]
  • MPI: a Message-passing Interface Standard Version 3.0
  • MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS
    심형진 [2012]
  • Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
    S. G. Hong [2011]
  • Hexagonal CMFD formulation employing triangle-based polynomial expansion nodal kernel
    J. Y. Cho [2001]
  • HELIOS Methods
  • Development of a sensitivity and uncertainty analysis code for high temperature gas-cooled reactor physics based on the generalized perturbation theory
    T. Y. Han [2015]
  • Development of a Multi-group Neutron Cross Section Library Generation System for PWR
    K. S. Kim [2008]
  • Development of HELIOS/CAPP code system for the analysis of pebble type VHTR cores
    H. C. Lee [2010]
  • Development of HELIOS/CAPP code system for the analysis of block type VHTR cores
    H. C. Lee [2012]
  • DeCART v1.2 User’s Manual
    J. Y. Cho [2007]
  • Compact nuclear power source critical experiments and analysis
  • Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculations
    조진영 [2002]
  • CRX : a code for rectangular and hexagonal lattices based on the method of characteristics
    S. G. Hong [1998]
  • CASMO-4 characteristic method for two-dimensional PWR and BWR core calculations
    K. Smith [2000]
  • Axial SPNand radial MOC coupled whole core transport calculation
    J. Y. Cho [2007]
  • Assessment and improvement of DeCART depletion calculation for VHTR fuel elements
    H. C. Lee [2012]
  • Application of the Gaussian quadrature to the azimuthal angle discretization in MOC
    H.C. Lee [2012]
  • APOLLO2 YEAR 2010
  • A statistical analysis of the double heterogeneity problem
    R. Sanchez [1991]
  • A nodal expansion method with spatially coupled effects incorporated into the transverse leakage approximation
    M. H. Chang [1989]
  • A new procedure to generate resonance integral table with an explicit resonance interference for transport lattice codes
    K. S. Kim [2011]