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

অনুরূপ উপাদানগুলি

• Status and perspective of two-phase flow modelling in the neptune multiscale thermal-hydraulic platform for nuclear reactor simulation /
  অনুযায়ী: Bestion, Dominique.
• Development of best practice guidelines for CFD in nuclear reactor safety /
  অনুযায়ী: 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 /
  অনুযায়ী: Smith, B.L..
• Analyses of fluid flow and heat transfer inside calandria vessel of candu-6 reactor using CFD /
  অনুযায়ী: Yu, Seon-Oh.