연구동향 분석

Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

Guo Hui Huo Xingkai Feng Kuaiyuan Gu Hanyang 2022년

논문상세정보
인용/피인용
' Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Neutronics
  • OpenMC
  • Start-up tests
  • VVUQ
  • benchmark
  • cefr
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
93 0

0.0%

' Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests' 의 참고문헌

  • Technical Specifications for Neutronics Benchmark of CEFR Start-Up Tests
    X. Huo [2019]
  • Selected VERA Core Physics Benchmarks in OpenMC
  • Preliminary coupling of the Monte Carlo code OpenMC and the multiphysics object-oriented simulation environment for analyzing Doppler feedback in Monte Carlo simulations
    M. Ellis [2017]
  • OpenMC : a state-of-the-art Monte Carlo code for research and development
  • Nuclear data processing capabilities in OpenMC
    P. Romano [2017]
  • Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation
  • Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation
    Xianan Du [2020]
  • Multi-core performance studies of a Monte Carlo neutron transport code
  • Molten Salt Reactors and Thorium Energy
  • Influence of Nuclear Data Library on Neutronics Benchmark of China Experimental Fast Reactor Start-Up Tests
    H. Guo [2022]
  • Handbook of Generation IV Nuclear Reactors, Woodhead Publishing Series in Energy
    C. F. Smith [2016]
  • Handbook of Generation IV Nuclear Reactors
    P. Tsvetkov [2016]
  • Fast Reactor Database 2006 Update (No. IAEA-TECDOC-1531)
    IAEA [2006]
  • Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent
  • Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark