CN-122021007-A - Steam generator local three-dimensional two-phase flow analysis and calculation method and system

CN122021007ACN 122021007 ACN122021007 ACN 122021007ACN-122021007-A

Abstract

The invention provides a method and a system for analyzing and calculating a partial three-dimensional two-phase flow of a steam generator, wherein a geometric model of the steam generator is divided into a heat transfer tube bundle region and a partial structure region, the high flow velocity phenomenon caused by the partial structure region is considered, the heat transfer tube bundle region and the partial structure region are calculated in a coupling way through boundary conditions of the geometric model of the steam generator, and the partial high flow velocity phenomenon of a part of heat transfer tubes of the steam generator can be accurately analyzed through introducing the partial structure region into model calculation, so that the vibration and abrasion problems possibly caused by the flow of the heat transfer tubes can be accurately predicted.

Inventors

YANG QING
YAO YANGUI
WU JIANBANG
ZHANG WEI
LIU CHANG
TANG LICHEN
LI CHEN
ZHANG YICHENG
ZHAO YU
Kang Xiaoxuan

Assignees

上海核工程研究设计院股份有限公司

Dates

Publication Date: 20260512
Application Date: 20260122

Claims (10)

1. A method for analyzing a partial three-dimensional two-phase flow of a steam generator, comprising: establishing a steam generator geometric model based on the structure of the steam generator; dividing the geometric model of the steam generator into a heat transfer tube bundle area and a local structure area; and taking the high flow velocity phenomenon caused by the local area into consideration, and carrying out coupling calculation on the heat transfer tube bundle area and the local structure area by combining the boundary condition of the geometric model of the steam generator.
2. The method of analyzing local three-dimensional two-phase flow of a steam generator according to claim 1, wherein the heat transfer tube bundle area is modeled by a porous medium mode, the resistance of the heat transfer tube bundle to the secondary side fluid is added to the coupling calculation with the local structural area by a distributed resistance coefficient model mode, and the heating effect of the heat transfer tube bundle to the secondary side fluid is added to the coupling calculation with the local structural area by a distributed heat source model mode.
3. The method of claim 2, wherein the model of the distributed resistance coefficient comprises two constitutive relations along the tube bundle and the transverse tube bundle according to the flow direction, or comprises two constitutive relations of a single-phase flow and a vapor-liquid two-phase flow according to the two-phase state.
4. The method of claim 2, wherein the heat transfer coefficients of the distributed heat source model are differentiated according to flow direction and two-phase state, and the heat transfer coefficients along the tube bundle and the transverse tube bundle are combined according to square relationship to obtain the final heat transfer coefficient.
5. A method of analyzing a partial three-dimensional two-phase flow of a steam generator according to claim 1, wherein the partial structured area is meshed with an unstructured mesh.
6. A method of analyzing a partial three-dimensional two-phase flow of a vapor generator as set forth in claim 1 wherein said boundary conditions of said vapor generator geometric model include inlet flow rate, inlet pressure, inlet temperature, outlet pressure temperature.
7. A steam generator local three-dimensional two-phase flow analysis system, comprising: the model building module is used for building a steam generator geometric model based on the structure of the steam generator; The dividing module is used for dividing the geometric model of the steam generator into a heat transfer tube bundle area and a local structure area; And the calculation module is used for carrying out coupling calculation on the heat transfer tube bundle area and the local structure area by taking the high flow velocity phenomenon caused by the local area into consideration and combining the boundary condition of the geometric model of the steam generator.
8. A computer device comprising a processor, a memory and a bus, the memory storing machine-readable instructions executable by the processor, the processor in communication with the memory via the bus when the computer device is in operation, the machine-readable instructions when executed by the processor performing a steam generator partial three-dimensional two-phase flow analysis method according to any one of claims 1 to 6.
9. A computer readable storage medium, characterized in that the computer readable storage medium has stored thereon a computer program which, when executed by a processor, performs a steam generator local three-dimensional two-phase flow analysis method according to any one of claims 1 to 6.
10. A computer program product comprising a computer program which, when executed by a processor, implements the method of any of claims 1-6.

Description

Steam generator local three-dimensional two-phase flow analysis and calculation method and system Technical Field The invention belongs to the field of nuclear power, and particularly relates to a method and a system for analyzing and calculating a local three-dimensional two-phase flow of a steam generator. Background The statements in this section merely provide background information related to the present disclosure and may not necessarily constitute prior art. The steam generator is one of the main devices of the nuclear power station, and has the functions of transferring the heat generated by the reactor to the two loops through the heat transfer pipe of the steam generator, heating the water fed by the two loops into steam and pushing the steam turbine generator to generate electricity. In the operation process of the steam generator, the situation that the heat transfer pipe and the supporting plate or the heat transfer pipe and the vibration-resistant strip are worn to a certain extent often occurs, and the heat transfer pipe is broken sometimes and finally, so that the operation safety of the nuclear power station is seriously affected. For the completed and operated steam generator, after the abrasion depth of the heat transfer pipe exceeds the limit value, the heat transfer pipe is treated in a pipe blocking mode, the secondary side structure of the steam generator is not optimized and improved, and a large number of pipe blocking can influence the heat exchange efficiency of the steam generator. The existing technology mainly uses hardware facilities, for example, a digital simulation platform of a steam generator is proposed in a general-purpose patent CN112507521A in the patent, so that the full-range management of design and research and development is realized, a digital simulation platform and research and development environment are provided for the design and analysis of the steam generator, the patent focuses on the design and development flow of the steam generator, and a local three-dimensional two-phase flow field calculation method of the steam generator is not involved. The patent CN110057865A of Harbin engineering university provides a marine steam generator secondary side boiling heat transfer analysis device, which comprises a test section and a loop component device, and focuses on the test research device and does not relate to a marine steam generator local three-dimensional two-phase flow field analysis method. A thermal hydraulic analysis test system for a small steam generator is provided by a western-style traffic university patent CN107293340A, belongs to the technical field of nuclear power steam generator equipment, comprises a two-loop simulation device, obtains the performance operation parameters of the steam generator by measuring the temperature, the pressure and the flow of the fluid of the steam generator, and is mainly used for a device for carrying out test research on the steam generator and does not relate to a local three-dimensional two-phase flow field analysis method of the steam generator. In addition, in the traditional calculation analysis, a local three-dimensional two-phase flow field on the secondary side of the steam generator and the influence of the flow field on the abrasion of the heat transfer tube have been studied to a certain extent, computational fluid dynamics software is generally adopted, and the heat transfer and mass transfer characteristics of the secondary side of the whole steam generator, such as heat flux, fluid velocity distribution, temperature distribution, cavitation share, mixture density distribution and the like, are obtained through calculation by a three-dimensional two-phase numerical simulation method. However, in practical power station operation experience, it is found that the typical steam generator computational fluid dynamics software does not capture local high flow velocity phenomenon, and certain deviation appears in the evaluation of flow-induced vibration and abrasion phenomena of part of heat transfer tubes, and the traditional steam generator secondary side local three-dimensional two-phase flow field computing method has certain limitation. Disclosure of Invention In order to overcome the defects in the prior art, the invention provides a method and a system for analyzing and calculating a local three-dimensional two-phase flow of a steam generator, which can accurately analyze the local high flow velocity phenomenon of a part of heat transfer tubes of the steam generator by introducing a local structural area into model calculation, so that the problems of vibration and abrasion caused by the flow of the heat transfer tubes possibly occurring can be predicted more accurately. To achieve the above object, a first aspect of the present invention provides a method for analyzing and calculating a partial three-dimensional two-phase flow of a steam generator, comprising: establishing a steam generator geome