Focal Interest
Focal Interest

Nuclear reactor physics and engineering

External reference: https://openalex.org/T10597

  1. Full-resolution model reproduces key MSRE flow and neutron data
    Full-resolution multiphysics simulation of the Molten Salt Reactor Experiment couples neutronics with thermal-hydraulics to reproduce experimental behavior and reveal three-dimensional flow.
  2. Analytical model estimates MHD pressure losses in lead-lithium flow
    Analytical model and CFD validation for MHD pressure drop in lead-lithium flows for fusion reactor breeding blankets under variable magnetic field conditions.
  3. Catalytic Oxidation of Hydrogen in Air Streams
    High school research on catalytic oxidation of hydrogen in air streams, examining catalyst performance and oxidation efficiency under controlled laboratory conditions.
  4. Greedy hybrid pathway balances emissions, cost, and reliability
    Explore Taiwan's energy transition pathways using greedy algorithm optimization to balance nuclear power, emissions reduction, costs, and grid stability through 2050.
  5. Cr and rare-earth grey phases form in doped fuel models
    Synchrotron spectroscopy reveals chromium and lanthanide speciation in Cr-doped uranium dioxide fuels, showing perovskite secondary phases remain structurally stable under radiation exposure.
  6. A CFD S S T k − ω − k θ − ε θ four parameter heat transfer turbulence model for the 19-pin fuel assembly in LBE cooled reactors
    Four-parameter turbulence model for predicting heat transfer in lead-bismuth cooled fast reactors, addressing nonlinear Prandtl number behavior in liquid metal coolants.
  7. Structural choices strongly affect CFETR tritium breeding performance
    Neutronics modeling of CFETR HCCB blanket demonstrates structural design optimization yields substantial tritium breeding ratio gains; material composition changes show limited benefit.
  8. Graphite modification reduced molten LBE infiltration
    Polycarbosilane impregnation and pyrolysis process significantly reduces molten LBE infiltration into nuclear graphite, improving impermeability for lead-cooled fast reactor coolant channels.
  9. Passive safety systems handled the cold-leg LBLOCA in the SCW-SMR study
    Study analyzes cold-leg LBLOCA for supercritical water SMR using parametric analysis, demonstrating passive safety systems effectively manage the accident without active high-pressure injection.
  10. A snippet-based algorithm for practical covariance estimation in Feynman- α analysis
    Snippet-based algorithm for covariance estimation in Feynman-α analysis addressing correlations introduced by neutron count bunching with reduced computational and data requirements.