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Nuclear-grade pipeline fatigue damage evaluation method based on fluid-solid coupling analysis

A fatigue damage and fluid-structure coupling technology, applied in special data processing applications, instruments, electrical and digital data processing, etc., can solve problems such as unguaranteed margins and too conservative calculation results, and achieve accurate, reliable and efficient fast calculation. Engineering calculation requirements, easy-to-use effects

Pending Publication Date: 2019-11-19
SUZHOU NUCLEAR POWER RES INST +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

When calculating the thermal transient stress, a convective heat transfer coefficient corresponding to the Green's function library is conservatively determined according to the flow boundary conditions for convolution calculation. The calculation result is too conservative and cannot guarantee the margin in the nuclear power plant license renewal demonstration

Method used

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  • Nuclear-grade pipeline fatigue damage evaluation method based on fluid-solid coupling analysis
  • Nuclear-grade pipeline fatigue damage evaluation method based on fluid-solid coupling analysis
  • Nuclear-grade pipeline fatigue damage evaluation method based on fluid-solid coupling analysis

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0059] Example 1 Establishment of Green's function based on fluid-solid coupling analysis and calculation under a certain main circuit flow rate and top-fill flow rate

[0060] 1.1 Establishment of analysis process

[0061] First, the steady-state fluid-structure coupling calculation based on the average temperature is performed, and then the transient temperature field calculation based on the average temperature step is performed. The structural steady-state multi-physics fluid-solid coupling analysis and the transient multi-physics fluid-solid coupling analysis are completed in the same ANSYS Workbench project, and the same grid is used in the steady-state and transient analysis. Use the Fluent steady-state flow field and temperature field to initialize the Fluent transient calculation. The temperature field calculated by the Fluent steady-state is imported as a thermal load into the steady-state structural analysis (Static Structural) to calculate the steady-state thermal ...

Embodiment 2

[0093] Example 2 Flow Network Setting and Node Green's Function Calculation

[0094] Five flow rates are set for the flow rate of the main pipeline and the flow rate of the topfill to cover their respective flow ranges, and the stress Green's function of each flow node is established according to the above method.

Embodiment 3

[0095] Embodiment 3 Interpolation calculation of Green's function and calculation of transient thermal stress

[0096] The interpolation calculation of temperature Green's function and stress Green's function is carried out according to formulas (1)-(18), and the calculation of transient temperature and transient thermal stress is carried out according to formulas (19)-(20). details as follows:

[0097]First at each flow Q 2j Down, to Q 1 The flow rate is interpolated to get Q 1 Q 2j Green's function data required under the flow combination.

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[0108] Then according to Q 1 Q 2j Green's function data pair Q under flow combination 2 The flow rate is interpolated to get Q 1 Q 2 Green's function data required under the flow combination.

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Abstract

The invention discloses a nuclear-grade pipeline fatigue damage evaluation method based on fluid-solid coupling analysis. Taking double flow boundaries as an example, the method comprises the following steps: constructing a flow network according to a flow change range of an analysis part, and constructing a normalized temperature response Green function and a stress response Green function undera temperature step on each flow combination node; carrying out interpolation calculation on a temperature Green function and a stress Green function according to the flow of the flow boundary at the moment t; and according to a Green function method, carrying out temperature and stress response rapid calculation on the temperature step load on the flow boundary at the moment t, and evaluating fatigue damage of the nuclear grade pipeline according to a result obtained through calculation. The Green function is directly obtained according to fluid-solid coupling calculation, hot zone division and convective heat transfer coefficient calculation are avoided, the method is close to the actual flow and heat transfer conditions to the maximum extent, heat transfer nonlinear characteristics are fully considered in Lagrange interpolation calculation, and rapid calculation of the Green function is more accurate, reliable and efficient.

Description

technical field [0001] The invention specifically relates to a method for evaluating nuclear-grade pipeline fatigue damage based on the results of rapid calculation of nuclear-grade pipeline thermal stress Green's function based on fluid-solid coupling analysis. Background technique [0002] On-line fatigue monitoring of nuclear-grade pipelines needs to use the Green’s function method to quickly calculate its thermal transient stress. However, in the thermal transient process, there are also transient flow boundary conditions in addition to fluid temperature transients. changes, which in turn lead to changes in the convective heat transfer coefficient. Due to the complexity of the nuclear-grade pipeline structure, the flow field change law of the fatigue analysis part is complicated, and it is difficult to accurately divide the heat zone with a constant convective heat transfer coefficient. In the past, the area related to the analysis site can only be roughly divided into ...

Claims

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Application Information

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IPC IPC(8): G06F17/50
Inventor 余伟炜陈明亚薛飞陈志林张彦召高炳军陈旭高红波
Owner SUZHOU NUCLEAR POWER RES INST
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