Status and perspective of two-phase flow modelling in the neptune multiscale thermal-hydraulic platform for nuclear reactor simulation /

Eitemau Tebyg

• Development and preliminary assessment of a three-dimensional thermal hydraulics code, CUPID /
• Extension of CFD codes application to two-phase flow safety problems /
  gan: Bestion, D.
• Experiments on the performance sensitivity of the passive residual heat removal system of an advanced integral type reactor /
• A simple analytical method for nonlinear density wave two-phase instability in a sodium-heated and helically coiled steam generator /
  gan: Kim, Seong-O.
• Development of interfacial area transport equation /
  gan: Ishii, Mamoru.