Time step acceleration method for refining transient neutron transport calculation
A technology for calculating time and time steps, which is applied in calculation, computer-aided design, design optimization/simulation, etc., and can solve problems such as influence effectiveness, unstable numerical calculation, and insufficient acceleration effect
Pending Publication Date: 2022-03-25
HARBIN ENG UNIV
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Problems solved by technology
The TML method uses the traditional CMFD method to solve the neutron flux density of the coarse network, and the drastic numerical changes in the transient neutron transport calculation will make the natural defects of the traditional CMFD easier to show, which will lead to the instability of the numerical calculation and affect the Accelerated effectiveness
In addition, the TML method only introduces temporal and spatial resolution, and the acceleration effect is not sufficient
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[0024] The technical solutions in the embodiments of the present invention will be clearly and completely described below. Obviously, the described embodiments are only some of the embodiments of the present invention, but not all of them. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative efforts fall within the protection scope of the present invention.
[0025] The applicant of this application believes that in order to improve the computational efficiency of high-fidelity transient neutron transport calculations, commonly used solutions mainly include:
[0026] (1) Simply expand the transport time step to reduce the calculation amount of transient neutron transport, and then improve the calculation efficiency of transient neutron transport. But for the time differential term, using the differential form instead of the differential form will inevitably introduce errors, and the error introduced by t...
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The invention provides a time step acceleration method for transient neutron transport calculation of a nuclear reactor, which introduces the thought of time step acceleration on the basis of a standard PCQM method, and proposes a multi-stage PCQM method: carrying out multi-stage division on the time step of transient neutron transport calculation, establishing systems with different space, energy and angle resolutions under different time resolutions, and carrying out multi-stage calculation on the time step of transient neutron transport calculation. Neutron flux density characteristics of different resolutions are respectively captured by high-fidelity neutron transport calculation, multi-group gCMFD, single-group gCMFD and exact point reactor dynamics (EPK), and then solutions of a high-order system on a large time step are corrected step by step by using rapid solution of a low-order system on a small time step, so that accurate high-fidelity neutron transport calculation can be carried out under the large time step. And effective time step acceleration is realized.
Description
technical field [0001] The invention relates to the field of neutron transport calculation, in particular to a time step acceleration method for nuclear reactor transient neutron transport calculation. Background technique [0002] At present, the acceleration methods for high-fidelity transient neutron transport calculation mainly include: standard predictive-correction quasi-static method, TML method, improved predictive-correction quasi-static method, etc. Among them, the standard estimation and correction quasi-static method refers to: decomposing the neutron flux density into an amplitude function and a shape function. In the estimation step, a high-fidelity transient transport solution is carried out with a large time step to obtain the estimated neutron flux density and kinetic parameters. Calculate the resulting magnitude function to correct the neutron flux density. The standard estimation and correction quasi-static method uses the point pile kinetic equation to ...
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IPC IPC(8): G06F30/28G06F30/25G06F111/04G06F113/08G06F119/12
CPCG06F30/28G06F30/25G06F2111/04G06F2113/08G06F2119/12
Inventor 朱雁凌郝琛康乐李佩军周晓宇
Owner HARBIN ENG UNIV