Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method

Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR

(2017) Mingjun Wang et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical simulation of flow and mixing in ROCOM facility using uniform and non-uniform inlet flow velocity profiles

(2014) M. Boumaza et al.   NUCLEAR ENGINEERING AND DESIGN

The development of Module In-vessel degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario

(2014) Jun Wang et al.   PROGRESS IN NUCLEAR ENERGY

Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000

(2012) Mingjun Wang et al.   ANNALS OF NUCLEAR ENERGY

Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR™: CFD investigations and comparison with experimental results

(2011) Victor Petrov et al.   NUCLEAR ENGINEERING AND DESIGN

Experiments at the mixing test facility ROCOM for benchmarking of CFD codes

(2007) S. Kliem et al.   NUCLEAR ENGINEERING AND DESIGN