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Thermal hydraulic transient calculation method suitable for sodium water once-through steam generator

A steam generator, thermal hydraulic technology, applied in the direction of calculation, computer-aided design, instrument, etc., can solve the problem of only applicable, etc., achieve the effect of wide applicable objects and ensure the accuracy of the solution

Active Publication Date: 2020-09-18
XI AN JIAOTONG UNIV
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  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The currently existing thermal-hydraulic transient calculation programs for sodium-water once-through steam generators are either only applicable to integral steam generators or only to modular steam generators

Method used

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  • Thermal hydraulic transient calculation method suitable for sodium water once-through steam generator
  • Thermal hydraulic transient calculation method suitable for sodium water once-through steam generator
  • Thermal hydraulic transient calculation method suitable for sodium water once-through steam generator

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Embodiment Construction

[0024] Below in conjunction with accompanying drawing, the present invention is described in further detail:

[0025] like figure 1 As shown, a thermal-hydraulic transient calculation method suitable for sodium-water once-through steam generators includes the following steps:

[0026] Step 1: Determine the geometric parameters of the steam generator, including the length, inner and outer diameters, pitch, and number of heat transfer tubes.

[0027] The thermal-hydraulic transient calculation is the thermal coupling calculation on both sides of sodium and water on the determined geometric structure of the steam generator. The calculation of parameters such as the heat transfer capacity of the steam generator, the heat transfer coefficient of the sodium side and the water side all require the geometric parameters of the steam generator.

[0028] Step 2: Establish a single-pipe model of the steam generator, and use the fixed grid method to divide the fluid control body.

[002...

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Abstract

The invention discloses a thermal hydraulic transient calculation method of a sodium water once-through steam generator. The method comprises the following steps: determining geometric parameters of asteam generator; establishing a steam generator single-tube model, and dividing a control body by adopting a fixed grid method; setting initial values of thermal hydraulic parameters in each controlbody; establishing a steam generator system equation set; discretizing the equation set based on a staggered grid and a finite difference method; obtaining an ordinary differential equation set according to a heat exchange and pressure drop formula and a fluid physical property function; and solving the simplified steam generator system equation set by adopting a Gear numerical solution method according to a given boundary condition to obtain a thermal hydraulic parameter value in each control body at each moment. The method is suitable for modular and integral sodium-water once-through steamgenerators, is convenient to operate, high in universality, flexible to use and high in precision, can completely meet the thermal-hydraulic transient calculation requirement of the sodium-water once-through steam generator, and can provide a software basis for independent design of the sodium-cooled fast reactor in China.

Description

technical field [0001] The invention belongs to the thermal-hydraulic technical field of fast neutron reactor steam generators, and in particular relates to a thermal-hydraulic transient calculation method suitable for sodium-water once-through steam generators. Background technique [0002] Sodium-cooled fast reactor (SFR), as one of the limited research and development cores of the fourth-generation nuclear energy system, has the advantages of improving the utilization rate of uranium and transmuting long-lived radioactive waste. To date, there are more than 400 years of reactor operating experience based on experimental, prototype and demonstration sodium-cooled fast reactors around the world. The sodium-water once-through steam generator (OTSG) is a key component of the sodium-cooled fast reactor nuclear power plant, which is of great significance to the safe operation of the nuclear power plant. The steam generator is the boundary between sodium and water, and it trans...

Claims

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Application Information

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IPC IPC(8): G06F30/28G06F30/23G21C17/00G06F113/08G06F119/14G06F119/08
CPCG21C17/00G06F30/23G06F30/28G06F2113/08G06F2119/08G06F2119/14Y02E30/30
Inventor 张大林许荣栓王式保王成龙田文喜苏光辉秋穗正
Owner XI AN JIAOTONG UNIV
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