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Simulation method for heat exchange performance of straight tube type once-through steam generator

A steam generator and heat transfer performance technology, applied in the field of nuclear power, can solve problems such as inaccurate calculation results of heat transfer tube wall temperature, complex heat transfer calculation methods, etc.

Active Publication Date: 2015-08-12
HARBIN ENG UNIV
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  • Abstract
  • Description
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  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The purpose of the present invention is to provide a simulation method for the heat transfer performance of straight-tube once-through steam generators, which solves the problems of complicated heat transfer calculation methods and inaccurate calculation results of heat transfer tube wall temperature in current once-through steam generators

Method used

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  • Simulation method for heat exchange performance of straight tube type once-through steam generator
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  • Simulation method for heat exchange performance of straight tube type once-through steam generator

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Embodiment Construction

[0052] The present invention will be described in detail below in combination with specific embodiments.

[0053] The invention adopts the distributed parameter method to establish a mathematical model of the once-through steam generator based on five calculation areas, and realizes automatic segmental calculation in the simulation process to accurately analyze the heat transfer characteristics of the once-through steam generator.

[0054]Step 1, establish the physical model of the once-through steam generator:

[0055] Set the structural parameters and boundary conditions of the once-through steam generator, as shown in Table 1 and Table 2 below.

[0056] Table 1 Structural parameters of once-through steam generator

[0057]

[0058] Table 2 Boundary conditions of 100% working condition

[0059]

[0060] Combined with the actual working engineering of the once-through steam generator, the following assumptions are made: 1) Simplify the tube bundle of the once-through ...

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Abstract

The invention discloses a simulation calculation model for the heat exchange performance of a straight tube type once-through steam generator and an algorithm thereof. According to the simulation calculation model, a one-dimensional homogeneous flow mathematic model of the once-through steam generator based on heat transfer partition is established, a secondary side heat exchange process is divided by adopting appropriate distinguishing conditions, a once-through steam generator heat exchange simulation program based on MATLAB (matrix laboratory) software is developed independently on the basis of the simulation calculation model, and the simulation for the steady state heat exchange performance of the once-through steam generator under different working conditions is carried out. The programming difficulty is simplified and reduced, automatic judgment and piecewise calculation can be realized, the range and position of wall temperature uprise and the lengths of heat exchange tubes in all heat transfer areas under different working conditions are accurately predicted, and thus a serious working area of the once-through steam generator is obtained. Theoretical support can be provided for preventing the accidents, such as overtemperature tube burst, of the once-through steam generator.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and relates to a simulation method for the heat exchange performance of a straight-tube direct-flow steam generator. Background technique [0002] The once-through steam generator is an important equipment in nuclear reactors, and has been mostly used in integrated pressurized water reactors in recent years. Since the working medium on the secondary side will be evaporated to dryness during the process of being heated from supercooled water to superheated steam, it is easy to cause the heat transfer tube to rupture, which in turn leads to serious problems such as shutdown of the entire reactor and nuclear radiation leakage. Therefore, the safety and reliability of once-through steam generators during the operation of nuclear power plants has attracted great attention. [0003] In 1982, Walter applied the first-order one-dimensional conservation equation, and used the drift flow model to de...

Claims

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Application Information

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IPC IPC(8): G06F17/50
Inventor 孙宝芝干依燃张国磊李晓明宋福元李彦军杨龙滨韩怀志张鹏
Owner HARBIN ENG UNIV
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