Computing method for full-coupling conjugate heat transfer of U-shaped pipe steam generator

Abstract

The invention discloses a U-shaped tube steam generator full-coupling conjugate heat transfer calculation method. The method mainly comprises the following steps: 1, simplifying geometric models of a primary side and a secondary side of a U-shaped tube steam generator; 2, geometric calculation areas and corresponding nodes of fluid domains and solid domains on the primary side and the secondary side of the U-shaped pipe steam generator are divided; 3, conjugate heat transfer boundary transfer of fluid domains and solid domains on the primary side and the secondary side of the U-shaped pipe steam generator; 4, establishing calculation models of fluid domains and solid domains on the primary side and the secondary side of the U-shaped pipe steam generator; and 5, integrally discretizing the equation set of each region in a full-coupling mode and solving the equation set. According to model simplification, an actual U-shaped pipe steam generator is simplified into a form facilitating geometric region and grid division; establishing a simplified geometric model, and dividing grids; defining an intermediate variable, and realizing boundary condition transmission between a solid domain and a fluid domain; establishing mathematical models in a solid domain and a fluid domain respectively; and finally, simulating the conjugate heat transfer process of the U-shaped tube steam generator by adopting full-coupling discrete solution.

Description

technical field [0001] The invention belongs to the field of thermal-hydraulic characteristic analysis of nuclear reactors, and in particular relates to a fully coupled conjugate heat transfer calculation method for U-shaped tube steam generators. Background technique [0002] The steam generator is the hub of the primary and secondary loops of the PWR, and is the heat transfer boundary of the primary and secondary loop working fluids. Ensuring its integrity plays a vital role in the operation of the PWR nuclear power plant. At present, due to the complexity of solving the two-phase fluid equation and the conjugate heat transfer process, weak coupling or strong coupling solution methods are often used for the conjugate heat transfer of steam generators at home and abroad, that is, the fluid domain and the solid domain are solved separately. The so-called separation solution, the first step is to calculate the fluid domain equation. At this time, the boundary of the solid dom...

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Problems solved by technology

The so-called separation solution, the first step is to calculate the fluid domain equation. At this time, the boundary of the solid domain is regarded as a constant, and the variable parameters of the fluid domain are calculated, and then passed to the solid domain to calculate the heat conduction equation of the solid domain. At this time, the fluid domain parameters Treated as a constant, the calculated conjugate heat transfer process cannot update variables synchronously, and there is a hysteresis effect of variables

In addition, the traditional system programs at home and abroad deal with the heat conduction of heat transfer tube bundles relatively rough, ignoring the axial heat conduction of the solid domain, and only considering the transverse one-dimensional heat conduction process, the results are rough, and it is impossible to accurately simulate the U-tube primary and secondary sides. Yoke heat transfer process

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