Extension of CFD codes application to two-phase flow safety problems /

Míreanna Comhchosúla

• Status and perspective of two-phase flow modelling in the neptune multiscale thermal-hydraulic platform for nuclear reactor simulation /
  le: Bestion, Dominique.
• Development of best practice guidelines for CFD in nuclear reactor safety /
  le: Mahaffy, J.
• Toward an accurate approach for the prediction of the flow in a T-junction : URANS /
• Assessment of CFD codes used in nuclear reactor safety simulations /
  le: Smith, B.L..
• Measurement of the single and two phase flow using a newly developed average bidirectional flow tube /