The article provides an overview of the reactor dynamics code DYN3D. The code comprises
various 3D neutron kinetics solvers, a thermal-hydraulics reactor core model and a thermo …

Interest in circulating fuel reactors (CFRs), particularly molten salt reactors (MSRs) of the
fluid fuel type, has been growing in the last two decades. Starting with a resurgence of …

The development of spatial dynamics code for molten salt reactors (MSRs) is reported in this
paper. The graphite-moderated channel type MSR–one of the 'Generation IV'concepts–was …

This paper presents the coupled code system of PROTEUS-NODAL and SAM developed for
multiphysics simulation of molten salt reactors (MSRs). The coupling was made under the …

The molten salt reactor (MSR) flowing-fuel simulation capability of the Griffin-Pronghorn-
coupled multiphysics code system developed by Idaho National Laboratory (INL) was …

In molten salt reactors (MSRs), the liquid fuel salt circulates through the primary loop and a
part of the delayed neutron precursors (DNPs) decays outside the reactor core. To model …

Nuclear reactors operated with liquid fuel may have several remarkable advantages and
features. The most developed reactor system in this category is the Molten Salt Reactor. It …

The molten salt reactor (MSR) is one of the six advanced reactor concepts declared by the
Generation IV International Forum (GIF), which can be characterized by attractive attributes …

This paper presents the PROTEUS-NODAL capabilities developed for modeling and
simulation of molten salt reactors (MSRs) with flowing fuel. Steady-state and transient …

This paper reports about the DYN1D-MSR code development and dynamics studies of the
molten salt reactors (MSR)–one of the 'Generation IV International Forum'concepts. In this …