Studies and Codes on Molten Salt Reactors


Studies and Codes on Molten Salt Reactors

Koch, R.; Křepel, J.; Grundmann, U.; Rohde, U.

The renewed interest on MSR systems has stimulated the development of computational tools assigned for analysis and simulation of MSR systems. The code system is a tool developed at Forschungszentrum Rossendorf for the analysis of burn-up behavior and transient simulation of Molten Salt Reactors. The computing method is based on the coupling between the well-known Monte Carlo transport code MCNP-4C2 and the burn-up code ORIGEN 2.1. In the second part the contribution shows applications of the system DYN3D-MSR dynamics code for Molten Salt Reactors, which is based on FZR two groups diffusion code DYN3D designed for dynamics calculation of light water reactors.

Keywords: Molten-Salt Reactor; MSR; Monte-Carlo Code; MCNP; Burnup; ORIGEN; Reactor Dynamics; DYN3D

  • Lecture (Conference)
    Technical Meeting of the Co-ordinated Research Project on " ... Incineration of Radioactive Waste", 22.-26.11.2004, Hefei, China

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