Publications Repository - Helmholtz-Zentrum Dresden-Rossendorf

2 Publications
Dynamics of molten salt reactors
Krepel, J.; Rohde, U.; Grundmann, U.;
Dynamics of the Molten Salt Reactor, one of the 'Generation IV International Forum' concepts, was studied in this paper. The graphite-moderated channel type MSR was selected for the numerical simulation. The MSR represents a liquid fueled reactor and its dynamics is very specific because of two physical peculiarities: the delayed neutrons precursors are drifted by the fuel flow and the fission energy is immediately released directly into the coolant. Presently, there are not many accessible numerical codes appropriate for the MSR simulation, therefore the DYN3D-MSR code was developed based on the Light Water Reactor dynamics code DYN3D. It allows calculating of full 3D transient neutronics in combination with parallel channel type thermal-hydraulics. The code was validated on experimental results of Molten Salt Reactor Experiment (from Oak Ridge National Laboratory) and applied to several transients typical for the liquid fuel system. Those transients were initiated by reactivity insertion, by overcooled or overfueled fuel slug, by the fuel pump start-up or coast-down, or by the blockage of single fuel channels. In these considered transients, the response of the MSR is characterized by the immediate change of the fuel temperature according to the power level. This causes fast feedback reactivity insertion, which is negative in the case of power increase. On the other hand, the graphite response is slower and its feedback coefficient is in some cases positive. The addition of erbium to the graphite can ensure the negative feedback and inherent safety features. The DYN3D-MSR code has been shown to be an effective tool for MSR dynamics studies.
Keywords: MSR, molten, salt, reactor, dynamics, MSRE, MSBR
  • Contribution to proceedings
    International Congress on Advances in Nuclear Power Plants - ICAPP 2006, 04.-08.06.2006, Reno, United States
  • Lecture (Conference)
    International Congress on Advances in Nuclear Power Plants - ICAPP 2006, 04.-08.06.2006, Reno, United States

Publ.-Id: 8338 - Permalink