[3B09-11] Advanced Reactor

[3B10] Evaluation of the inherent neutron source and power density in the Intermediate Heat Exchanger of a small chloride-fueled molten salt fast reactor

*Willem F.G. van Rooijen¹, Jamiyansuren Terbish² (1. Univ. of Fukui, 2. National University Of Mongolia)

Keywords:Molten Salt Reactor, Intermediate Heat Exchanger, Delayed neutron fraction, Monte Carlo Method

In the primary system of a chloride fuel molten salt fast reactor, there is no moderator, and the reactivity of the system is entirely determined by the size and shape of the reactor vessel. Since the fuel is in a liquid form, a part of the delayed neutrons which are formed in the core decay outside of the core. That is to say, the entire primary system becomes one big sub-critical reactor system. Since the intermediate heat exchangers (IHX) are quite large, the multiplication of neutrons in the IHX can become considerable, and the multiplication factor and power density in the IHX must be evaluated. In this research, we designed an IHX and used the Monte Carlo method to evaluate the neutron flux and power density in the IHX.