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An optimization method of a nuclear reactor system analysis program suitable for a multi-loop pressurized water reactor

A nuclear reactor and system analysis technology, applied in multi-programming devices, program control design, design optimization/simulation, etc., can solve complex problems and achieve the effect of improving computing efficiency

Active Publication Date: 2020-12-25
NUCLEAR POWER INSTITUTE OF CHINA
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  • Application Information

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Problems solved by technology

However, when the magnitude of nodes and the size of the matrix increase significantly, even dimensionality reduction is relatively complicated

Method used

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  • An optimization method of a nuclear reactor system analysis program suitable for a multi-loop pressurized water reactor
  • An optimization method of a nuclear reactor system analysis program suitable for a multi-loop pressurized water reactor
  • An optimization method of a nuclear reactor system analysis program suitable for a multi-loop pressurized water reactor

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Embodiment

[0050] Such as Figure 1 to Figure 3 As shown, the present invention is applicable to the optimization method of the nuclear reactor system analysis program of the multi-loop pressurized water reactor. For the research object, it is divided into different calculation modules, and the pressure solution matrix of different division modules is respectively established to reduce the calculation scale of a single matrix; Computational efficiency.

[0051] The specific implementation steps of the inventive method are as follows:

[0052] S1: Discretize the mass, momentum and energy equations of the vapor phase and liquid phase of the nuclear reactor system analysis program in a certain form (such as mass and discretization, mass difference discretization, momentum and discretization, momentum difference discretization, energy and discretization, energy difference discretization, etc. , depending on the specific nuclear reactor system analysis program.)

[0053] S2: For the discre...

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Abstract

The invention discloses an optimization method of a nuclear reactor system analysis program suitable for a multi-loop pressurized water reactor, which includes combining a modular thought to block a multi-loop pressurized water reactor system loop, and dividing a whole nuclear reactor primary loop system into a loop N (N = 1, 2...), a reactor body and the like; respectively establishing pressure solving matrixes of M control bodies of each division module to form an M * M (or 2M * 2M and the like) matrix equation set; in combination with a parallelization idea, solving N + 1 M * M (or 2M * 2Mand the like) matrix equation sets on different computing nodes to obtain vapor / liquid phase pressure of each control body of different division modules, then exchanging pressure parameters obtained by computing by the division modules, and continuing iterative computation until convergence is achieved; and finally, calculating a mass enthalpy value matrix equation to obtain parameters such as node enthalpy values, cavitation share and the like at a new moment. According to the method, the dimension of the large matrix is effectively reduced, and the calculation efficiency is improved.

Description

technical field [0001] The invention relates to the technical field of thermal hydraulic design and safety analysis of nuclear reactors, in particular to an optimization method for nuclear reactor system analysis programs applicable to multi-loop pressurized water reactors. Background technique [0002] For the multi-loop pressurized water reactor system circuit, when using the nuclear reactor system analysis program for modeling and analysis, after dividing the number of nodes, a large sparse matrix is ​​usually formed for overall calculation, which requires high computer memory and greatly reduces the calculation speed, thereby affecting Design analysis progress. [0003] At present, the large-scale matrix solving algorithms for nuclear reactor system analysis programs at home and abroad are mainly divided into two categories: direct solution and iterative solution, and a series of mature algorithm libraries have been developed, such as PETSc, SuperLU, BPLU, MA18, etc. Ho...

Claims

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Application Information

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IPC IPC(8): G06F9/50G06F17/16G06F17/12G06F30/20
CPCG06F9/5027G06F17/16G06F17/12G06F30/20
Inventor 于洋刘东宋小明郭凤晨冷贵君李庆王雅峰芦韡卢宗健庞勃唐雷曹国海王媛美张思原袁光辉
Owner NUCLEAR POWER INSTITUTE OF CHINA
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