Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis

Author:

Wang Jincheng,Wang Qin,Ding MingORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference152 articles.

1. Coupled neutronic/thermal-hydraulic hot channel analysis of high power density civil marine SMR cores;Alam;Ann. Nucl. Energy,2019

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3. Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis;Aufiero;Chem. Eng. Sci.,2014

4. Serpent – openfoam coupling in transient mode: simulation of a godiva prompt critical burst;Aufiero;Math. Comput. Div. Am. Soc. Top. Meet. (M&C,2015

5. Aufiero, M., Fratoni, M., 2016. Development of Multiphysics Tools for Fluoride-Cooled High-Temperature Reactors, in: PHYSOR 2016, Sun Valley, ID, May 1–5, 2016.

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