DYN3D-MSR

Computer Code for Steady-State and Transient Analysis of Molten Salt Reactors

Introduction:

Dynamics of Molten Salt Reactors – one of the "Generation IV" concepts – have been studied in the Reactor Safety Department . 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.

Publications

Fuel cycle advantages and dynamics features of liquid fueled MSR
Krepel, J.; Hombourger, B.; Fiorina, C.; Mikityuk, K.; Rohde, U.; Kliem, S.; Pautz, A.
Annals of Nuclear Energy 64(2014), 380-397

Dynamics of Molten Salt Reactors
Krepel, J.; Grundmann, U.; Rohde, U.; Weiss, F.-P.
Nuclear Technology 164(2008), 34-44

DYN3D-MSR spatial dynamics code for Molten Salt Reactors
Krepel, J.; Rohde, U.; Grundmann, U.; Weiss, F. P.
Annals of Nuclear Energy 34(2007), 449-462

Analysis of MSR Benchmark by Using the Code DYN1D-MSR
Krepel, J.; Grundmann, U.; Rohde, U.
Annual Meeting on Nuclear Technology 2004, Düsseldorf, 25. - 27. May 2004

Develoment and Verification of Dynamics Code for Molten Salt Reactors
Krepel, J.; Grundmann, U.; Rohde, U.
Proceedings of ICONE 12: 12th International Conference on Nuclear Engineering April 25-29, 2004, Arlington, Virginia, USA

Benchmark of Dynamics Simulation Tool for Molten Salt Reactors
Delpech, M.; Dulla, S.; Garzenne, C.; Kophazi, J.; Krepel, J.; Lebrun, C.; Lecarpentier, D.; Mattioda, F.; Ravetto, P.; Rineiski, A.; Schikorr, M.; Szieberth, M.
Proceedings of the international conference GLOBAL 2003, 2182-2187, New Orleans, LA, November 2003

Development and Verification of a Reactor Dynamics Code for Molten Salt Reactors with Flowing Fuel
Krepel, J.; Grundmann, U.; Rohde, U.
Annual Meeting on Nuclear Technology 2003, Berlin, 15. - 17. May 2003