The JFNK method for the PWRs transient simulation considering neutronics, thermal hydraulics and mechanics

' The JFNK method for the PWRs transient simulation considering neutronics, thermal hydraulics and mechanics' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • JFNK Preconditioning
  • Neutronics/TH/Mechanics
  • multi-physics
  • transient
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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' The JFNK method for the PWRs transient simulation considering neutronics, thermal hydraulics and mechanics' 의 참고문헌

  • The coupled kinetic and thermal-hydraulic three dimensional code system NLSANMT/COBRA-IV for PWR core transient analysis
  • Parallel algorithms and software for nuclear, energy, and environmental applications. Part II: multiphysics software
  • Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis
    Yijun Zhang [2018]
  • NEACRP 3-D LWR Core Transient Benchmark:Final Specifications
  • Multiphysics simulations: challenges and opportunities
  • Multiphysics simulation of fast transients with the FINIX fuel behaviour module 2
  • Light water reactor fuel performance modeling and multi-dimensional simulation
  • Light Water Reactor Fuel Analysis Code FEMAXI-6 (Ver. 1). Detailed Structure and User's Manual
  • Jacobian-free NewtoneKrylov methods : a survey of approaches and applications
  • Jacobian-Free Newton-krylov coupling methods for nuclear reactors
  • Iterative Methods for Sparse Linear Systems
    Youcef Saad [2009]
  • High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis
    J. Magedanz [2015]
  • Heat Transfer Coefficient between UO 2 and Zircaloy-2
    A.M. Ross [1962]
  • GMRES : a generalized minimal residual algorithm for solving nonsymmetric linear systems
    Youcef Saad [1986]
  • FRAPCON-3.4: a Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup
  • Efficient simultaneous solution of multi-physics multi-scale nonlinear coupled system in HTR reactor based on nonlinear elimination method
    Han Zhang [2018]
  • Development of a general coupling interface for the fuel performance code TRANSURANUSeTested with the reactor dynamics code DYN3D
    L. Holt [2015]
  • Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation
    Youqi Zheng [2017]
  • Anisotropic azimuthal power and temperature distribution as a driving force for hydrogen redistribution
  • An assessment of coupling algorithms in HTR simulator TINTE
    Han Zhang [2018]
  • Advanced multiphysics coupling for LWR fuel performance analysis
    J. D. Hales [2015]
  • A verification exercise in multiphysics simulations for coupled reactor physics calculations