Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor

Automated core design code development for a lead‐cooled fast reactor and its core optimization

(2020) Xiao Luo et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

3D thermal hydraulic characteristics analysis of pool-type upper plenum for lead-cooled fast reactor with multi-scale coupling program

(2020) Zeren Zou et al.   NUCLEAR ENGINEERING AND DESIGN

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

(2020) Muhammad Ramzy Altahhan et al.   NUCLEAR ENGINEERING AND DESIGN

Development and application of CFD and subchannel coupling analysis code for lead‐cooled fast reactor

(2019) Chi Wang et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications

(2019) Xuebei Zhang et al.   ANNALS OF NUCLEAR ENERGY

Preliminary design of a medium-power modular lead-cooled fast reactor with the application of optimization methods

(2018) Hongli Chen et al.   INTERNATIONAL JOURNAL OF ENERGY RESEARCH

Transient safety analysis of M2LFR-1000 reactor using ATHLET

(2018) Chong Shen et al.   Nuclear Engineering and Technology

Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model

(2017) Kan Wang et al.   PROGRESS IN NUCLEAR ENERGY

Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform

(2016) Carlo Fiorina et al.   ANNALS OF NUCLEAR ENERGY

Coupling a CFD code with neutron kinetics and pin thermal models for nuclear reactor safety analyses

(2015) Zhao Chen et al.   ANNALS OF NUCLEAR ENERGY

Comparison of different coupling CFD–STH approaches for pre-test analysis of a TALL-3D experiment

(2015) Angel Papukchiev et al.   NUCLEAR ENGINEERING AND DESIGN

GeN-Foam: a novel OpenFOAM ® based multi-physics solver for 2D/3D transient analysis of nuclear reactors

(2015) Carlo Fiorina et al.   NUCLEAR ENGINEERING AND DESIGN

A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phénix Reactor Natural Circulation Test

(2014) R. Bavière et al.   NUCLEAR ENGINEERING AND DESIGN

CFD analysis of thermal stratification and sensitivity study of model parameters for k–ɛ model in a cylindrical hot plenum

(2012) Shyam S. Das et al.   NUCLEAR ENGINEERING AND DESIGN

CFD analysis of the MYRRHA primary cooling system

(2011) Matthias Vanderhaegen et al.   NUCLEAR ENGINEERING AND DESIGN