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In this study, building on the author's previous experience in the simulation of the MSRE system, a similar approach was used to model the dual fluid reactor design. The work was done using a modified version of the system code TRACE capable of simulating molten salt and metal flows and the transport of the neutron precursors with the flowing fuel, and the Monte Carlo based Serpent code to generate the appropriate core neutronic data used in the point kinetics models of TRACE. The authors coupled both codes Serpent and TRACE to calculate the steady-state power and temperature fields. Based on them, the authors have proposed an optimized geometry and flow rates for the reactor. With the optimized design, the results for several reactivity transient scenarios have been presented: step insertion reactivity and reactor over-and undercooled scenarios. The investigated transient scenarios show that the reactor is stable, self-regulating, and can withstand severe conditions.

Hanusek T. et al. E1-2017-91 Determining the Fast Neutron Flux Density and Transmutation Level Measurements in the ADS by the Use of a Threshold Nuclear Reaction The aim of the project was determining the fast neutron ux density by using data from the Quinta experiment (E + T RAW collaboration), which took place on 4 December 2015 at the Veksler and Baldin Laboratory of High Energy Physics (VBLHEP), the Joint Institute for Nuclear Research (JINR). The experimental assembly based on natural uranium and an aluminum cover was irradiated by a 660 MeV proton beam from the Phasotron, DLNP, JINR. To gain the knowledge about the neutron ux inside the experimental assembly, nuclear threshold reactions of (n, xn) type were used. This paper describes the Quinta assembly, experimental results, calibration procedure and average high energy neutron calculation based on yttrium (Y-89) isotopes production. In the future, results and conclusions from an experiment like this could be useful to design accelerator-driven subcritical systems (ADS) or other 4th generation fast reactors. The paper is based on the 2016 Student Summer Practice work at JINR. The investigation has been performed at the Veksler and Baldin Laboratory of High Energy Physics, JINR.

The aim of the project was the determining the Fast Neutron Flux Density and Transmutation Level measurements in the experimental assembly Quinta based on natural uranium, irradiated by 660 MeV proton beam from cyclotron "Phasotron" at the Laboratory of High Energy Physics, JINR Dubna. A threshold reactions Y 89 (n, xn) were used. This paper describes the Quinta assembly, experimental results from December 2015, and average high-energy neutron calculation based on Y 89 isotopes production. The better knowledge about neutron flux density is necessary to constructing the fourth generation nuclear reactors such as fast reactors (FR) and accelerator-driven subcritical systems (ADS).