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The Dual Fluid Reactor (DFR) is a fast reactor concept proposed by the Institute of Solid-state-and Nuclear physics (IFK) in Berlin. The design of DFR aims to combine the Gen-IV Molten Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR), which means that the molten-salt fuel is no more used as coolant while the heat is removed in a se...
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... spatial distribution of the neutron flux is plotted in Figs. 8 and 9, which are in the radial and axial directions, respectively. Fig. 8 shows the radial distribution comparison between the DFR and the smDFR with a comparable variant smDFR'-this has no back-flow fuel tubes in the reflector. The orientation of the fuel tube arrangement does not impact the calculations. The horizontal axis is labeled with the percentage of radial coordinates because the DFR and the smDFR ...
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... By using liquid lead, the dual fluid reactor has a high capability to transfer heat produced in the core and can be operated at a considerably high power density without any safety issues. The characteristics of the steady-state physics of the dual fluid reactor concept were investigated [5,6], and a comparative study of the two fuel options was conducted [7]. The distribution zone of the dual fluid reactor concept has been designed and analyzed from the perspective of thermal hydraulics [8,9]. ...
The small modular dual fluid reactor is a novel variant of the Generation IV molten salt reactor and liquid metal fast reactor. In the primary circuit, molten salt or liquid eutectic metal (U-Pu-Cr) is employed as fuel, and liquid lead works as the coolant in the secondary circuit. To design the control system of such an advanced reactor, the uncertainties of the employed computer model and the physicochemical properties of the materials must be considered. In this paper, a one-dimensional model of a core is established based on the equivalent parameters achieved via the coupled three-dimensional model, taking into account delayed neutron precursor drifting, and a power control system is developed. The performance of the designed controllers is assessed, taking into account the model and property uncertainties. The achieved results show that the designed control system is able to maintain the stability of the system and regulate the power as expected. Among the considered uncertain parameters, the reactivity coefficients of fuel temperature have the largest influence on the performance of the control system. The most optimized configuration of the control system is delivered based on the characteristics of uncertainty propagation by using the particle swarm optimization method.
... This concept takes advantage of the superb heat-transfer properties of lead, hence higher temperature and thermal efficiency, along with the continuous fueling and isotope separation features of liquid fuel and the inherent safety provided by a melting fuse plug to empty the reactor of fuel under accident conditions. A small modular DFR (2 MW) reactor is proposed [197]. This design is prompted as ''an effective waste incinerator and as an excellent thorium breeder'' [196]. ...
This paper reviews the smallness, modularity and reactor-design aspects of emerging small modular reactors (SMRs). It is shown that small (whether in physical size or power level) reactors are not new, but offer economic and flexibility advantages that allow their use in a variety of applications. The different definitions of modularity are reviewed, including modularity in design, process intensification, manufacturing and construction. It is shown that these forms of modularity when applied to SMRs have some advantages, but also have some challenges that need to be addressed if their full potential is to be realized. Even if these forms of modularity are not fully utilized, the lower power (≤300 MW electrical) of SMRs allows the formation of larger power plants by incremental addition of reactor units, in the so-called scale modularity. The paper reviews the unique features of emerging SMR designs, and compares them to those of the early era of nuclear power. It is shown that while many modern SMR designs incorporate well-proven features that were tested and proven in early reactors. others introduce aspects of Generation IV reactors, in terms of inherent and/or passive safety. Given the promise of SMRs as means to reduce greenhouse gas emissions and their ability to supply reliable and base-load power, the licensing of such reactors by national regulators will provide a boost to their acceptability and adaptability as a player in combating climate change.
The small modular dual fluid reactor (smDFR) adopts a mixture of liquid uranium and plutonium chloride as fuel, with lead as a coolant. With its smaller size, lower weight, and inherent safety, the smDFR can be used as a mobile energy supply for vehicles or ships. Analyses of the smDFR are still in the early stage based on a single or separated physical field, which can hardly capture the impact of the flowing fuel on the neutron field. The coupled neutronic-fluid dynamic calculation is needed for reliable multidimensional, multi-field distribution of the steady-state smDFR core property. In this work, the Monte Carlo code Serpent 2 and the CFD code Open-FOAM are coupled via a Python interface, whereby the neutron field information can be exchanged with the fluid field in a region-average manner. The correctness and reliability of the coupled code are verified with two cases in the pressurized water reactor background, and the results show good agreement. The coupled code is applied to the steady-state analyses of an smDFR, a single-channel case, and a 1/6-core case. The results show that the temperature distribution of the fuel and coolant caused a lower drift of the axial power peak compared to the uncoupled cosine shape power distribution. The 1/6-core results show that the peak temperature of the fuel reaches 980 K at the top-center of the reactor core. Moreover, the influence of fuel thermal properties and inlet velocity are studied with rated power. Through the comparison of mapping schemes, the results can identify the dependence of specific parameters and help to reduce mapping errors. This work shows that through a coupled neutronic-CFD code, the multidimensional and multi-physical fields of the smDFR can be better represented, providing important references for the future design and analyses of smDFR systems.
With a small molten salt lead-based reactor as its research object, this paper proposes a method combining Monte Carlo techniques and advanced optimization algorithms to realize the optimal design of the core. By selecting different core parameters and applying a multi-objective genetic algorithm, a more compact core design is achieved. Calculation results show that the proposed method can optimize the structure of a small molten salt lead-based reactor, realize the core optimization design under multi-objective constraints. The developed method can provide a favourable reference for the development and design of a new type of reactor.
The concept of a molten salt reactor began at the Oak Ridge National Laboratory (ORNL) in the United States. Due to its high energy densities, high operating temperatures, and distinguished safety characteristics compared to those of conventional water reactors, molten salt reactors are receiving increasing attention. The dual fluid reactor (DFR), as a new type of molten-salt lead-based reactor, has been studied in recent years because it combines features of molten salt and lead-based reactors. This article has carried out in-depth physical calculations on a small modular DFR (smDFR) variation proposed in previous studies, which is expected to be safer, easier and quicker to manufacture, more economically efficient, and more flexible in actual applications, especially for various mobile application solutions. Using Monte Carlo codes, an accurate three-dimensional model of smDFR was established, and core physical calculations such as critical effective multiplication factor, flux distribution, and power distribution were performed between codes. Static physical properties are obtained through critical calculations. It proves that the results from codes are consistent for the given case. The research results of this paper can also provide design reference for the development of small molten salt lead-based reactor.
