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CN-122024868-A - Simulation method of spent fuel dissolver, program product, electronic equipment and storage medium

CN122024868ACN 122024868 ACN122024868 ACN 122024868ACN-122024868-A

Abstract

The invention discloses a simulation method of a spent fuel dissolver, a program product, electronic equipment and a storage medium. The simulation method of the spent fuel dissolver comprises the steps of taking a preset surface area correction factor of a cutting block of a fuel rod, an initial parameter of the cutting block, and the volume and concentration of dissolving liquid in the dissolver as input parameters of a simulation model of the preset dissolver, wherein the surface area correction factor is used for correcting the unit surface area dissolution rate of the cutting block by the simulation model, the initial parameters comprise time intervals, cutting times and the mass of a single cutting block of the fuel rod, the simulation model is used for simulating the dissolution process of the cutting block according to the input parameters, and simulation results output by the simulation model are obtained and represent the dissolution process of the cutting block in the dissolver.

Inventors

  • YU TING
  • LU ZONGHUI
  • HE HUI
  • TANG HONGBIN

Assignees

  • 中国原子能科学研究院

Dates

Publication Date
20260512
Application Date
20260104

Claims (10)

  1. 1. A method of simulating a spent fuel dissolver, the method comprising: The method comprises the steps of taking a preset surface area correction factor of a cutting block of a fuel rod, an initial parameter of the cutting block, and the volume and concentration of dissolving liquid in a dissolver as input parameters of a simulation model of the preset dissolver, wherein the surface area correction factor is used for correcting the unit surface area dissolution rate of the cutting block by the simulation model, the initial parameters comprise time intervals, times and mass of single cutting block of the fuel rod, and the simulation model is used for simulating the dissolution process of the cutting block according to the input parameters; and obtaining a simulation result output by the simulation model, wherein the simulation result represents the dissolution process of the shear block in the dissolver.
  2. 2. The method of claim 1, wherein the simulation model computes the dissolution rate per unit surface area of the shear block as: wherein alpha is a surface area correction factor, k is a dissolution reaction equilibrium constant, E is reaction activation energy, R is a gas constant, T is a dissolution temperature, C HNO3 is a dissolution liquid concentration, and n is a reaction progression.
  3. 3. The method of claim 1, wherein the simulation results include a rate at which uranium in the shear block changes from a solid phase to a liquid phase, and wherein the simulation model computes a uranium ion generation rate as: Where α is a surface area correction factor, k is a dissolution reaction equilibrium constant, N is a reaction progression, C HNO3 is a dissolution solution concentration, N U is a concentration of uranium ions in the dissolution solution, N U,solid is an amount of undissolved solid uranium, and M U,i represents a mass of uranium added per batch of shearing.
  4. 4. The method of claim 1, wherein the simulation result includes a rate at which nitric acid in the dissolution liquid is consumed, and wherein the simulation model calculates a nitric acid consumption rate as: Wherein alpha is a surface area correction factor, k is a dissolution reaction equilibrium constant, N is a reaction progression, C HNO3 is a dissolution liquid concentration, beta is a uranium acid ratio, the uranium acid ratio represents a mole number of nitric acid required for complete dissolution of unit mole uranium, and N U,solid is an amount of undissolved solid uranium.
  5. 5. The method of claim 1, wherein the surface area correction factor has a value in the range of [0.6,1.4].
  6. 6. The method of claim 1, wherein the simulation results include time series data of uranium ion concentration in the dissolution liquid, time series data of nitric acid concentration, time series data of residual solid mass in the dissolution liquid, and time series data of nitrogen oxide release rate.
  7. 7. The method of claim 1, wherein obtaining simulation results output by the simulation model, the method further comprises: And determining the change relation of the concentrations of nitric acid and uranium along with time according to the simulation relation, and determining the change relation of the concentrations of uranium ions in the dissolution liquid along with time under the values of different surface area correction factors.
  8. 8. A computer program product comprising a computer program which, when executed by a processor, implements the steps of the simulation method of a spent fuel dissolver of any one of claims 1 to 7.
  9. 9. An electronic device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor, when executing the computer program, performs the steps of the method of simulating a spent fuel dissolver according to any one of claims 1 to 7.
  10. 10. A computer readable storage medium, characterized in that the computer readable storage medium stores a computer program comprising program instructions which, when executed by a processor, cause the processor to perform the steps of the simulation method of the spent fuel dissolver of any one of claims 1 to 7.

Description

Simulation method of spent fuel dissolver, program product, electronic equipment and storage medium Technical Field The invention relates to the technical field of spent fuel aftertreatment, in particular to a simulation method of a spent fuel dissolver, a program product, electronic equipment and a storage medium. Background In the process of nuclear fuel post-treatment PUREX, a dissolver is a key device for dissolving a sheared block into nitric acid to convert the sheared block from a solid form into a liquid form, and the operation process involves complex mass transfer, oxidation-reduction reaction and multiphase disturbance coupling. The mathematical model in the related art generally simplifies the shear block into an ideal cylinder for dissolution surface area calculation, and does not consider factors such as the roughness and the porosity of the surface of the core block, crushing damage caused by shearing and the like. The idealization assumption causes that the geometric surface area calculated by the model is not consistent with the actual effective dissolution surface area, so that the dissolution rate prediction generates deviation, the simulation result error is larger, and the dynamic behavior of the dissolution process is difficult to truly reflect. Disclosure of Invention In view of the above, the embodiments of the present invention provide a simulation method, a program product, an electronic device and a storage medium for a spent fuel dissolver. The technical scheme of the embodiment of the invention is realized as follows: In one aspect, an embodiment of the present invention provides a simulation method for a spent fuel dissolver, where the method includes: The method comprises the steps of taking a preset surface area correction factor of a cutting block of a fuel rod, an initial parameter of the cutting block, and the volume and concentration of dissolving liquid in a dissolver as input parameters of a simulation model of the preset dissolver, wherein the surface area correction factor is used for correcting the unit surface area dissolution rate of the cutting block by the simulation model, the initial parameters comprise time intervals, times and mass of single cutting block of the fuel rod, and the simulation model is used for simulating the dissolution process of the cutting block according to the input parameters; and obtaining a simulation result output by the simulation model, wherein the simulation result represents the dissolution process of the shear block in the dissolver. In the above scheme, the formula for calculating the dissolution rate of the shear block per unit surface area by the simulation model is as follows: wherein alpha is a surface area correction factor, k is a dissolution reaction equilibrium constant, E is reaction activation energy, R is a gas constant, T is a dissolution temperature, C HNO3 is a dissolution liquid concentration, and n is a reaction progression. In the above scheme, the simulation result includes a rate of uranium in the shear block from a solid phase to a liquid phase, and the formula of the simulation model for calculating the uranium ion generation rate is: Where α is a surface area correction factor, k is a dissolution reaction equilibrium constant, N is a reaction progression, C HNO3 is a dissolution solution concentration, N U is a concentration of uranium ions in the dissolution solution, N U,solid is an amount of undissolved solid uranium, and M U,i represents a mass of uranium added per batch of shearing. In the above scheme, the simulation result includes a rate at which nitric acid in the solution is consumed, and the formula of the simulation model for calculating the nitric acid consumption rate is: Wherein alpha is a surface area correction factor, k is a dissolution reaction equilibrium constant, N is a reaction progression, C HNO3 is a dissolution liquid concentration, beta is a uranium acid ratio, the uranium acid ratio represents a mole number of nitric acid required for complete dissolution of unit mole uranium, and N U,solid is an amount of undissolved solid uranium. In the above-described embodiment, the surface area correction factor has a value in the range of [0.6,1.4]. In the scheme, the simulation result comprises time sequence data of uranium ion concentration in the dissolution liquid, time sequence data of nitric acid concentration, time sequence data of residual solid mass in the dissolution liquid and time sequence data of nitrogen oxide release rate. In the scheme, the simulation result output by the simulation model is obtained, the method further comprises the steps of: And determining the change relation of the concentrations of nitric acid and uranium along with time according to the simulation relation, and determining the change relation of the concentrations of uranium ions in the dissolution liquid along with time under the values of different surface area correction factors. On the other hand,