Coupling method of metal fuel multiphysics model for metal cooled fast reactor
A metal fuel and multi-physics technology, applied in computational theoretical chemistry, instrumentation, chemical property prediction, etc., can solve problems such as the inability to simulate the performance changes of metal fuels, achieve powerful visualization functions, good precision, and simplify data analysis and data display The effect of the process
Active Publication Date: 2021-11-09
LINGDONG NUCLEAR POWER +3
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Problems solved by technology
However, COMSOL cannot handle the complete disappearance of the solution domain during the simulation calculation, which leads to an error when the gap coolant in the fuel core and cladding is completely squeezed out of the gap due to core expansion when simulating the early behavior of fuel irradiation and terminate the calculation, it is impossible to simulate the performance change of the metal fuel throughout the irradiation process
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[0074] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific implementation manners of the present invention will now be described in detail with reference to the accompanying drawings.
[0075] refer to figure 1 , the metal-cooled fast reactor metal fuel multi-physics model coupling method of an embodiment of the present invention uses the metal fuel active section 13 / 30 axial position to carry out two-dimensional axisymmetric modeling of the metal fuel and conducts radiation behavior simulation, analysis The coupled simulation analysis of the metal fuel multiphysics model at the axial position includes the following steps:
[0076] S1. Establish and couple the metal fuel multi-physics field coupling model in the irradiation process in COMSOL, and solve in COMSOL to obtain the change value of the temperature of the outermost fuel core with time in the early stage of metal fuel irradiation. Specifically...
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Abstract
The invention discloses a metal-cooled fast reactor metal fuel multi-physics field model coupling method, comprising the following steps: S1. Establishing and coupling the metal-fuel multi-physics field coupling model in the irradiation process in COMSOL, and solving in COMSOL to obtain the metal fuel The change value of the outermost temperature of the fuel core with time in the early stage of irradiation; S2, derive the change value of the outermost temperature of the fuel core with time, and use the least square method to fit the outermost temperature of the fuel core to obtain the temperature function ; S3. Remove the interstitial coolant heat transfer model in the metal fuel multi-physics coupling model, and use the outermost temperature function of the metal fuel as the boundary condition of the fuel core heat transfer model, and obtain the metal fuel during the entire irradiation process. Irradiation performance parameters. Based on the COMSOL multi-physical field coupling simulation platform, the invention introduces the metal fuel irradiation behavior model into the field of metal fuel performance analysis and simulation simulation through strong coupling, and realizes accurate simulation of the metal fuel irradiation behavior.
Description
technical field [0001] The invention relates to the technical field of performance analysis and simulation of advanced fast reactor metal fuel, in particular to a multi-physical field model coupling method for metal-cooled fast reactor metal fuel. Background technique [0002] In recent years, in order to reduce the pressure on the storage of radioactive waste in LWR fuel, there has been strong international interest in the development of fast neutron reactors. Fast neutron reactors can burn long-lived actinides in LWR spent fuel to reduce nuclear waste. long-term radiation. As one of the fourth-generation reactors, metal fast reactors can incinerate long-lived actinide nuclides left over from thermal reactors, and can realize the proliferation of fissile materials while generating energy. The metal fuel for metal cold fast reactors, namely uranium-zirconium alloy (U-Zr) or uranium-plutonium-zirconium alloy (U-Pu-Zr) has the advantages of stronger proliferation and better s...
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IPC IPC(8): G16C20/30G16C10/00
Inventor 李文淮丁鹏段承杰王磊仇若翔林继铭石秀安
Owner LINGDONG NUCLEAR POWER