Thermal-hydraulics of a homogeneous molten salt fast reactor concept: experimental and numerical analyses
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Thermal hydraulics
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The aim of this work is to use a modified version of TRACE for a preliminary study of a molten salt reactor (MSR) system behavior for the steady-state, transient and accidental conditions so as to demonstrate the suitability of the TRACE code for MSR simulation. To this end the analysis and results from the MSRE (Molten Salt Reactor Experiment) were used as a reference case. The basic approach of this work is to couple the 1D thermal-hydraulic model for 3 loops and the 0D neutronic dynamics (point-kinetic model), which was solved by the ODE-solver built by "Control Blocks" offered in TRACE. Additionally, new working fluids, namely the molten salts, were added into the source code of TRACE. Most results of the simulations show good agreement with the ORNL reports as well as the previous study in recent years and the errors were predictable and in an acceptable range. Therefore, the necessary code modification of TRACE appears to be successful and will be refined further in order to investigate new MSR designs, such as MSFR and DFR.
TRACE (psycholinguistics)
Molten salt reactor
Solver
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Considering the fuel salt flow effect of the molten salt reactor,the delayed neutron precursors are drifted out of the core,which lead to a complex and highly coupled phyxical environment.A model of point-reactor neutron kinetics equation in combination with 2-D kinetics equations is presented for describing the stability in the molten salt reactor.In the steady-state operation conditions,dynamic response process of core temperature under the fuel negative feedback effect was simulated after introducing three step representation disturbances.The simulation results indicate that the core could quickly achieve stability under the negative feedback effect of temperature.Moreover,the flow characteristics of the fuel salt and the space effect of delayed neutron precursors were taken into consideration in this model,which was closer to the reality of the molten salt reactor core.
Neutron Transport
Molten salt reactor
Thermal hydraulics
Core model
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The Molten Salt Reactor (MSR) is the most important system suggested by Generation IV for the future direction in the nuclear reactor field. For more development of the MSR reactor, the core system inside the tube is proposed by naturally circulating molten fuel salt. The nonlinear kinetic equations form a linearized function and are obtained in state-space form. Reactivity feedback and delayed neutrons are extremely important for reactor control. In this paper, a thermal-hydraulic system for the commercial computation dynamic model is proposed. Currently, there is no commercial software to simulate the natural circulation flow. The proposed method can be easily employed to detect faults and can provide a feasible overall system performance.
Natural circulation
Thermal hydraulics
Molten salt reactor
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Molten Salt Reactor(MSR) was selected as one of the six innovative nuclear reactors by the Generation IV International Forum(GIF).The circulating-fuel in the can-type molten salt fast reactor makes the neutronics and thermo-hydraulics of the reactor strongly coupled and different from that of traditional solid-fuel reactors.In the present paper,a new coupling model is presented that physically describes the inherent relations between the neutron flux,the delayed neutron precursor,the heat transfer and the turbulent flow.Based on the model,integrating nuclear data processing,CAD modeling,structured and unstructured mesh technology,data analysis and visualization application,a three dimension steady state simulation code system(MSR3DS) for the can-type molten salt fast reactor is developed and validated.In order to demonstrate the ability of the code,the three dimension distributions of the velocity,the neutron flux,the delayed neutron precursor and the temperature were obtained for the simplified MOlten Salt Advanced Reactor Transmuter(MOSART) using this code.The results indicate that the MSR3DS code can provide a feasible description of multi-physical coupling phenomena in can-type molten salt fast reactor.Furthermore,the code can well predict the flow effect of fuel salt and the transport effect of the turbulent diffusion.
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A novel continuous molten-metal pretreament technology using swirling-reactors is recently proposed by Japanese Scientists. Reactor designing is a key problem for developing and applying this technology. Detailed information about the flow process in a reactor is then very necessory. In this paper, a mathematical model for numerically simulating two-phase molten-metal and particle flow is established. The models used include the k?e two-equation model for turbulent molten-metal flow and the random trajectory model for particle flow. The governing equations are solved by SIMPLER algorithm. The two-phase flow characteristics in a swirling-reactor are numerically studied. Detailed flow field of the molten metal and moving behavior of the particles in the reactor are obtained. Calculated results show that particles can be effectively dropped into molten metal flow using this type swirling-reactor. Particles and molten metal could be mixed well when adopting proper geometrical parameters and operating conditions. These results offer detailed scientific basis for designing and optimizing the hot metal pre-treatment technology.
Molten metal
Particle (ecology)
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Molten salt reactor
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Numerical methodology for sodium combustion has been developed for the safety evaluation of a liquid metal cooled fast reactor. The methodology includes fast-running zone model computer program, field model program for multi-dimensional thermalhydraulics, chemical reaction analysis program based on chemical equilibrium theory, and so forth. Phenomenological scale in sodium fire varies widely and it is impossible to deal with all the scales in one simulation. Therefore, multi-level modeling and detailed-level simulations develop numerical correlations that can be used in the zone model or field model codes. Simulations using numerically-derived correlations are effective way of safety analysis. Although the sodium combustion is a complex phenomenon, use of these computer programs gives better understanding of the coupled thermalhydraulics and chemical reaction.
Hydraulics
Thermal hydraulics
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Based on the MSFR (Molten Salt Fast Reactor) reactor concept presented within the framework of the EVOL (Evaluation and Viability of Liquid Fuel Fast Reactor System, EU FP7) international research project preliminary three-dimensional thermal-hydraulic analyses and the discussion of scaled experimental modelling will be presented. The MSFR concept is a single region, homogeneous liquid fuelled fast reactor. The reactor concept uses fluoride-based molten salts with fissile uranium and/or thorium and other heavy nuclei content with the purpose of applying the thorium cycle and the burn-up of transuranic elements. The concept has a single region cylindrical core with sixteen radial inlet and outlet nozzles located at the bottom and top of the core. The external circuit (internal heat exchanger, pump, pipes) is broken up into sixteen identical modules distributed around the core. Purpose of the three-dimensional computational fluid dynamics (CFD) calculations is to study the possibility of experimental investigation of the fluid flow in the core of the proposed MSFR concept using a scaled model and Particle Image Velocimetry (PIV) flow measurement technique. First the main properties of the proposed MSFR concept are introduced, and the information on other experimental thermal-hydraulic modelling of different reactors, including MSRE (Molten Salt Reactor Experiment) are summarised. With a scaled plexiglas MSFR model it would be possible to carry out flow field measurements under laboratory conditions using PIV method. Possible way of scaling are presented and a series of preliminary CFD calculations are discussed. Possibilities and limitations of such scaling and segmenting of a model and the use of water as substitute fluid for the experimental mock-up will be discussed. Objectives of such a measurement series would be validation, benchmarking of CFD calculations and codes, application of CFD modelling experience in the detailed thermal-hydraulic design of the MSFR concept, possible measurements for the study of specific problems or phenomena, for example refinement of inlet geometry, effects of internal structures, coolant mixing.
Molten salt reactor
Thermal hydraulics
Enriched uranium
Breeder reactor
Thorium Fuel Cycle
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Abstract There are various methods to store thermal energy from season to season. Because the density of energy storage in thermochemical materials is higher than the latent and sensible heat storage method, the thermochemical heat storage is considered the sufficient type. This paper provides a mathematical model of thermochemical storage process for thermochemical materials; potassium aluminum sulfate 12-hydrate (KAl(SO 4 ) 2 .12H 2 O). The software used is COMSOL Multiphysics Modelling Software. The model data is validated and compared with the previous experimental result. Furthermore, the temperature difference and the pressure over the material inside the reactor are investigated. There are seven designs for the bed. However, the inlet and outlet diameter of the bed is changed; there is any change in the volume and height of the bed. The model results present that the rise in entrance area decreases the charging time and rises the pressure drop inside the material. Case 4 is the best design from the charge time.
Multiphysics
Clathrate hydrate
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