Computer Code for Steady-State and Transient Analysis of Molten Salt ReactorsWissenschaftler:
Dynamics of Molten Salt Reactors – one of the "Generation IV" concepts – have been studied in the Department of Accident Analysis. The graphite-moderated channel type MSR was selected for the numerical simulation of the reactor with liquid fuel. The MSR dynamics is very specific because the fuel flow influences the delayed neutrons distribution. This reduce significantly the number of useable numerical codes, therefore the own code DYN3D-MSR was developed in HZDR. The code is based on the well-validated original HZDR dynamics code for LWR DYN3D. DYN3D-MSR allows calculating of full 3D neutronics transient in combination with parallel channel type thermal-hydraulics. The temperature field in the core is determined in the fuel salt and also in the graphite blocks, applying a special heat conduction model. By means of DYN3D-MSR, several transients typical for the liquid fuel system were analysed.
Dynamics of Molten Salt Reactors
DYN3D-MSR spatial dynamics code for Molten Salt Reactors
Analysis of MSR Benchmark by Using the Code DYN1D-MSR
Develoment and Verification of Dynamics Code for Molten Salt Reactors
Benchmark of Dynamics Simulation Tool for Molten Salt Reactors
Development and Verification of a Reactor Dynamics Code for Molten Salt Reactors with Flowing Fuel