Focal Interest
Focal Interest

Fusion materials and technologies

External reference: https://openalex.org/T10592

  1. 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.
  2. Brazing performed better than HIPing in divertor tests
    Study comparing brazing and Hot Isostatic Pressing methods for bonding copper interfaces in fusion reactor divertors, evaluating thermal performance and fatigue resistance.
  3. Predictive gyrokinetic simulations matched TCV edge-plasma data
    Fully predictive gyrokinetic simulations of tokamak edge turbulence using Gkeyll validate against TCV experiments and reveal how negative triangularity enhances confinement through E×B flow shear.
  4. 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.