A Calculation Method of Fluid-Structure Interaction in Nuclear Reactor Dispersed Plate Fuel Element Core

Abstract

The invention discloses a reactor core fluid-solid coupling calculation method of a nuclear reactor diffusion type plate fuel element. The method comprises the following steps: 1, establishing a nuclear reactor diffusion type plate fuel assembly fluid domain calculation model; 2, establishing a nuclear reactor dispersion type plate fuel assembly solid domain calculation model; 3, writing the irradiation effect in the burnup process of the reactor core into a solid finite element analysis program in a subprogram form; 4, carrying out steady-state calculation on the model in the step 1; 5, calling a result in the step 4 by utilizing an intermediate data exchange interface program, calling the calculation models in the step 1 and the step 2, continuously exchanging data between the fluid dynamics calculation program and the solid finite element analysis program subjected to secondary development in the step 3, and performing iterative calculation; and 6, performing iterative computation until the set computation termination time is reached, and stopping the computation. The detailed instantaneous thermal-hydraulic phenomena on the two sides of fluid and solid under the irradiation condition of the nuclear reactor plate-type fuel element core are obtained through calculation, and the method has important significance in design and safety analysis of a nuclear reactor.

Description

technical field [0001] The invention belongs to the technical field of method inventions, and in particular relates to a nuclear reactor core fluid-solid coupling calculation method of a diffuse plate-type fuel element. Background technique [0002] Dispersed plate fuel elements have many advantages and are widely used in research experimental reactors, naval reactors and small power reactors. In the late stage of reactor operation, due to the fast neutron radiation and the accumulation of fission products, there will be obvious radiation swelling, coupled with the thermal expansion of the fuel pellets and cladding, the thickness of the fuel element and the width of the flow channel will change, resulting in the The flow distribution, the temperature field of the fuel plate and the outlet temperature of the coolant deviate from the reactor design value. Under the condition of non-uniform irradiation, the fuel assembly is subjected to thermal, mechanical and irradiation effe...

AI Technical Summary

Problems solved by technology

[0004] Two-way fluid-structure coupling is a more accurate solution technology gradually developed with the continuous improvement of computer capabilities. It is currently in a period of vigorous development. However, for many finite element analysis software or program codes at home and abroad, such as ABAQUS, ANSYS, COMSOL, etc., these software and programs do not consider the effects of radiation swelling, densification or creep caused by radiation effects

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