Sub-channel analysis method combining resistance and energy distribution and containing grillwork mixing effect

Abstract

Provided is a sub-channel analysis method combining resistance and energy distribution and containing a grillwork mixing effect. The method comprises the steps of fitting a momentum source term relational expression and an energy source term relational expression which can reflect mixing performance of mixing grillwork key components by collecting experimental data of multiple mixing grillworks including a nuclear reactor core mixing grillwork to be analyzed under different working conditions, adding the momentum source term relational expression to a corresponding momentum conservation equation, and adding the energy source term relational expression to a corresponding energy conservation equation; obtaining more precise local thermal hydraulic parameters in a nuclear reactor core by solving a mass conservation equation, the momentum conservation equation and the energy conservation equation, and accordingly making the prediction of a critical heat flux(CHF) value and a CHF position more accurate. The sub-channel analysis method combining resistance and energy distribution and containing the grillwork mixing effect is not limited by a sub-channel program structure and solving method, can be widely applied to various types of sub-channel program calculation, and is mainly applied to a sub-channel program of a two-fluid model.

Description

technical field [0001] The invention belongs to the technical field of reactor fuel assembly fluid dynamics simulation and analysis, and in particular relates to a sub-channel analysis method that combines resistance and energy distribution and includes grid agitation effect. Background technique [0002] In the design and operation of nuclear power plants, critical heat flux (CHF) and critical power are one of the most important parameters that limit the operation of nuclear power plants. Below the critical power, the reactor can convert nuclear energy into electricity with maximum safety. The CHF of the fuel bundle is closely related to the local thermal-hydraulic parameters of the core. Due to the complex geometric structure of the reactor core channel and the operating conditions of a wide parameter range, an analytical solution for CHF cannot be given theoretically. [0003] The CHF relational expression of traditional nuclear fuel bundles is developed based on the exp...

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Problems solved by technology

However, the above method cannot accurately reflect the mixing characteristics of the grid, and cannot eliminate the inaccuracy in the calculation of local thermal-hydraulic parameters, because the form resistance coefficient relation used is still irrelevant to the geometric structure of the grid.

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