CN114065436B - Method for analyzing operation characteristics of steam generator with axial flow type preheater of nuclear power system - Google Patents

Method for analyzing operation characteristics of steam generator with axial flow type preheater of nuclear power system Download PDF

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CN114065436B
CN114065436B CN202111402013.8A CN202111402013A CN114065436B CN 114065436 B CN114065436 B CN 114065436B CN 202111402013 A CN202111402013 A CN 202111402013A CN 114065436 B CN114065436 B CN 114065436B
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田文喜
曾春杰
王明军
章静
秋穗正
苏光辉
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Xian Jiaotong University
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Abstract

The invention discloses a method for analyzing the operation characteristics of a steam generator with an axial-flow type preheater of a nuclear power system, which comprises the steps of 1, simplifying the structure of the steam generator according to a calculation target so as to determine a calculation domain; 2. establishing a corresponding geometric model and dividing grids by the determined calculation domain; 3. establishing an axial flow type preheater structural equation to capture the partitioned steam generator secondary side grid area; 4. marking an axial flow type preheater structure by adopting a grid marking method, and realizing the simulation of a steam generator with the axial flow type preheater structure; 5. and (3) carrying out thermodynamic and hydraulic calculation of the steam generator with the axial-flow type preheater based on the established model, and judging whether the grid in the step (2) needs to be encrypted and refined according to the accuracy of a calculation result until the model meets the calculation requirement. The invention provides a reference for designing an axial flow preheater in a steam generator and for operation.

Description

Method for analyzing operation characteristics of steam generator with axial flow type preheater of nuclear power system
Technical Field
The invention relates to the technical field of steam generators with axial flow preheaters in nuclear power systems, in particular to a method for analyzing the operation characteristics of the steam generator with the axial flow preheaters in the nuclear power system.
Technical Field
The steam generator is a core heat exchange device in a nuclear power system, which serves as a junction connecting primary and secondary side loops of a reactor, and is a pressure boundary and a heat transfer boundary of the primary loop. Whether the fission heat energy generated by the reactor core is efficiently transferred from the primary loop to the secondary loop depends on the economical efficiency of the nuclear power station. This therefore requires a high heat transfer efficiency of the steam generator. The axial flow type preheater arranged in the steam generator can enable the secondary side fluid (cold state water supply and recirculation water) at the cold and hot sides to carry out flow heat transfer relatively independently in the tube bundle area before the descending channel below the water supply pipeline reaches the top of the central partition plate, so that the heat transfer is enhanced in a mode of increasing the temperature difference of the primary side fluid and the secondary side fluid of the cold side heat transfer tube, and the heat transfer efficiency is improved.
The research on the intensified heat transfer of the axial-flow type preheater is less in China, and only the China nuclear power institute develops numerical simulation research: yang et al write one-dimensional SG thermodynamic hydraulic calculation analysis program based on FORTRAN 95 language, develop the heat exchange reinforcement research of the axial flow type preheater to the steam generator, but as the distribution situation of thermodynamic hydraulic parameters in the secondary side of the steam generator which can not be obtained by the one-dimensional program, meanwhile, the one-dimensional centralized parameter model is too simplified, and is only suitable for system level calculation; the comparative study of the thermal hydraulic parameters of a part of steam generators with and without an axial preheater was carried out by utilizing TBC software developed by Chengdu nuclear power station by Wuyang et al, but the model simplification is more and the reliability of the method is doubtful.
There is no disclosure of the relevant research at present abroad.
In summary, the current numerical simulation research on the axial flow type preheater is few, the implementation method of the related research is too simplified, and the accurate simulation of the thermal parameters of the steam generator with the axial flow type preheater is difficult to realize.
Disclosure of Invention
In order to solve the problems in the prior art, the invention provides a method for analyzing the operation characteristics of a steam generator with an axial flow preheater in a nuclear power system, which can realize the introduction of an axial flow preheater structure on a grid model of the steam generator without the axial flow preheater, can greatly reduce the workload of re-grid division and the grid division difficulty of a local structure, and simultaneously ensures better grid quality; the invention can be used for developing a comparison research on the introduction of the axial flow type preheater structure, researching the enhanced heat exchange effect of the axial flow type preheater on the steam generator, researching the height of the central baffle plate of the optimal axial flow type preheater and the distribution ratio of cold and hot side water supply, and providing reference for designing the axial flow type preheater in the steam generator and the operation.
In order to achieve the above purpose, the invention adopts the following technical scheme:
a method for analyzing the operation characteristics of a steam generator with an axial flow type preheater of a nuclear power system comprises the following steps:
step 1: analyzing the flow heat transfer process inside the steam generator, determining a computational domain and building a geometric model:
the flow process of the secondary side fluid of the steam generator is as follows: the secondary side fluid flows into the descending ring section through the water supply device, and the flowing direction is downward; the annular gap at the bottom of the descending ring section flows into the U-shaped tube bundle area, and the flowing direction is changed to be upward; the secondary side fluid becomes gas-liquid two phases after heat exchange in the U-shaped tube bundle area, and finally enters a steam-water separator; the flow process of the primary side fluid of the steam generator is as follows: fluid flows upwardly through the tube sheet from the inlet lower plenum and is then distributed by the tube sheet to each of the U-tubes on the primary side; the primary side fluid exchanges heat with the secondary side fluid in the process of flowing in the U-shaped pipe, and then flows out after being collected to an outlet cavity through a pipe plate from the outlet end of the U-shaped pipe; thus, the calculation domain for the steam generator is determined as: the secondary side comprises a descending loop section, a U-shaped tube bundle area and a steam-water separator inlet area, wherein a water supply inlet is arranged at the top of the descending loop section, namely the water level of the water supplied by the steam generator; the primary side comprises an inlet lower chamber, a tube plate, a U-shaped tube bundle area and an outlet lower chamber; then, a geometric modeling software is adopted to build a geometric model for the calculation domain, wherein the modeling of the U-shaped tube bundle area and the tube plate is simplified into an integral inverted U-shaped channel;
step 2: grid division is carried out on the geometric model established in the step 1, a grid model of a steam generator calculation domain is established, the coincidence of a central axis and a z axis of the whole grid is required to be ensured, and the subsequent grid marking is facilitated; the U-shaped tube bundle area and the grid of the tube plate area are processed into a porous medium model;
step 3: analyzing the structure of an axial flow preheater used in a steam generator, determining the implementation method: the main structure of the axial flow type preheater in the steam generator consists of two parts, namely a semi-cylindrical double-layer sleeve arranged on a descending ring section on the cold side of the steam generator and a central baffle arranged at the junction of the cold side and the hot side of a tube bundle region of the steam generator; the two-part structure ensures that secondary side fluid from the descending ring section of the steam generator to the area at the height of the central partition plate of the tube bundle area independently flows and exchanges heat in the cold side area or the hot side area, improves the average heat exchange temperature difference of the first side and the second side, and realizes the enhanced heat transfer; according to the characteristics, solid areas are arranged in the descending ring section area and the central area of the tube bundle area of the grid of the steam generator to realize the independent flow heat exchange function of the secondary side fluid in the cold side area or the hot side area respectively;
step 4: the grid marking method realizes the axial flow type preheater structure of the steam generator:
according to the structure of the axial flow type preheater, the grid marking area is provided with a tube bundle area and a descending ring section area, which are respectively as follows:
tube bundle zone central baffle grid marking:
assuming a tube bundle area radius R t The bottom plane of the tube bundle zone is at z=z 0 Plane, x > 0, is the hot side of the steam generator and vice versa, creates a thickness delta in the tube bundle region t The central partition board with the height h has a grid marking model as follows:
wherein x, y and z are the coordinate positions of the grids, and care needs to be taken that the thickness of the central baffle is not smaller than the minimum grid size of the area; the grid satisfying the above positional relationship is marked as a central separator;
descending ring section double-layer sleeve grid marking:
assuming that the inner ring radius of the descending ring section is R at different heights id (z) semi-cylindrical double-layer sleeve radius of axial flow preheater is R a (z) in the descending loop sectionEstablishing a double-layer sleeve structure with the same height as the descending ring section, wherein a grid marking model is as follows:
and->
Wherein delta r The thickness of the single grid is the area of the descending ring segment;
the grid marking model of the axial flow type preheater structure in the steam generator is characterized in that after the original steam generator grid is marked, a marking area is converted from a fluid area into a solid area, meanwhile, the conversion enables a water supply inlet at the top of a descending ring section to be separated into two parts, a double-layer sleeve surrounding area is set as a cold side inlet, and the rest part is a hot side inlet; the mesh model of the steam generator with the axial-flow type preheater is built through the steps 2 to 4;
step 5: definition of the drag coefficient of the descending loop section with axial flow preheater structure:
the steam generator numerical model established based on the porous medium model is coarser in grid division, and cannot reflect the additional resistance introduced by the axial flow type preheater structure of the descending ring section, and the additional resistance is realized by introducing corresponding resistance coefficients into the model, wherein the resistance coefficients are obtained by adopting the existing empirical relation and the existing experimental data analysis;
step 6: and (3) calculating thermal hydraulic parameters of the steam generator with the axial-flow type preheater:
and (3) carrying out thermodynamic and hydraulic numerical calculation on the established grid model with the axial-flow type preheater steam generator based on the computational fluid mechanics model, carrying out error analysis on the obtained calculation result and the test result, when the precision meets the requirement, successfully establishing the grid model with the axial-flow type preheater steam generator, and when the precision does not meet the requirement, returning to the step (2), adjusting grids, carrying out grid encryption operation, then continuing the follow-up operation, and repeatedly iterating until the calculation precision requirement is met.
The invention relates to a numerical simulation method capable of simulating the operation characteristics and the enhanced heat exchange effect of a steam generator with an axial flow type preheater in a nuclear power system, which has the following overall beneficial effects:
1) The invention can carry out grid marking on the grid of the existing steam generator to realize the axial-flow type preheater structure, thereby greatly reducing the workload;
2) According to the invention, an axial-flow type preheater structure is not required to be considered when the initial steam generation grid is established, so that grid division is simplified, local structures are reduced, the grid quality is improved, and the calculation accuracy is facilitated;
3) According to the invention, the grid marking model can be simply modified, so that the heights of the central partition plates of different axial flow preheaters are realized, the influence study of the heights of the different central partition plates on the enhanced heat exchange effect is conveniently carried out, and a reference is provided for the design of the axial flow preheaters;
4) The realization method of the invention has strong universality and can be suitable for numerical calculation models of steam generators of different types;
5) The invention can be used for carrying out the comparative research of the steam generator with or without the axial flow type preheater, and the research result can be used for providing reference for the improvement and upgrading work of the existing steam generator in the aspect of intensified heat exchange.
Drawings
FIG. 1 is a flow chart of an axial flow preheater model building process technique route of the present invention;
fig. 2 is a schematic diagram of the calculation domain of the steam generator according to the model of the present invention.
Fig. 3 is a schematic view of the calculated area section A-A of the steam generator according to the model of the present invention in fig. 1.
The areas and structures marked in the drawings are respectively: the device comprises a 1-inlet lower chamber area, a 2-descending loop section area, a 3-steam-water separator inlet area, a 4-semi-cylindrical double-layer sleeve, a 5-U-shaped tube bundle area, a 6-central baffle plate, a 7-tube plate, an 8-outlet lower chamber area, a 9-hot side water supply inlet and a 10-cold side water supply inlet.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.
Step 1: analyzing the flow heat transfer process inside a typical vertical natural circulation steam generator to determine the computational domain and build a corresponding geometric model:
the flow process of the secondary side fluid of the steam generator is as follows: the secondary side fluid flows into the descending ring section through the water supply device, and the flowing direction is downward; the annular gap at the bottom of the descending ring section flows into the U-shaped tube bundle area, and the flowing direction is changed to be upward; the secondary side fluid becomes gas-liquid two phases after heat exchange in the U-shaped tube bundle area, and finally enters a steam-water separator; the flow process of the primary side fluid of the steam generator is as follows: fluid flows upwardly through the tube sheet from the inlet lower plenum and is then distributed by the tube sheet to each of the U-tubes on the primary side; the primary side fluid exchanges heat with the secondary side fluid in the process of flowing in the U-shaped pipe, and then flows out after being collected to an outlet cavity through a pipe plate from the outlet end of the U-shaped pipe; thus, the calculation domain for the steam generator is determined as shown in fig. 2: the secondary side comprises a descending loop section 2, a U-shaped tube bundle section 5 and a steam-water separator inlet area 3, wherein the water supply inlet is arranged at the water level of the steam generator and is arranged at the top of the descending loop section; the primary side comprises an inlet lower plenum 1, a tube sheet 7, a U-shaped tube bundle section 5 and an outlet lower plenum 8; then, establishing the calculation domain by adopting geometric modeling software, wherein the modeling of the U-shaped tube bundle area and the tube plate is simplified into an integral inverted U-shaped channel;
step 2: grid division is carried out on the geometric model established in the step 1, a grid model of a steam generator calculation domain is established, the coincidence of a central axis and a z axis of the whole grid is ensured, and the subsequent grid marking is facilitated; the U-shaped tube bundle area and the grid of the tube plate area are processed into a porous medium model;
step 3: analyzing the structure of an axial flow preheater used in a steam generator, determining the implementation method: the main structure of the axial flow type preheater in the steam generator is composed of two parts, as shown in figure 2, namely a semi-cylindrical double-layer sleeve 4 arranged on the descending ring section of the cold side of the steam generator, and a central baffle 6 arranged at the junction of the cold side and the hot side of the tube bundle region of the steam generator; the two-part structure enables the secondary side fluid from the descending ring section of the steam generator to the area at the height of the central baffle plate of the tube bundle area to exchange heat independently in the cold side area or the hot side area, improves the average heat exchange temperature difference of the first side and the second side, and realizes the enhanced heat transfer; according to the characteristics, solid areas are arranged in the descending ring section area and the central area of the tube bundle area of the grid of the steam generator to realize the independent flow heat exchange function of the secondary side fluid in the cold side area or the hot side area respectively;
step 4: the grid marking method realizes the axial flow type preheater structure of the steam generator:
according to the structure of the axial flow type preheater, the grid marking area is provided with a U-shaped tube bundle area and a descending ring section area, which are respectively as follows:
u-shaped tube bundle area central baffle grid marking:
assume that the radius of the U-shaped tube bundle area is R t The bottom plane of the U-shaped tube bundle zone is at z=z 0 Plane, x > 0, is the hot side of the steam generator and vice versa, creates a thickness delta in the tube bundle region t (thickness of single grid of the area), central baffle with height h (1/2 height of steam generator is taken), and the grid marking model is as follows:
wherein x, y and z are the coordinate positions of the grid; the grid satisfying the above positional relationship is marked as a central separator;
descending ring section double-layer sleeve grid marking:
assuming that the inner ring radius of the descending ring section is R at different heights id (z) semi-cylindrical double-layer sleeve radius of axial flow preheater is R a (z) establishing a double-layer sleeve structure with the same height as the descending ring section in the descending ring section area, wherein a grid marking model is as follows:
and->
Wherein delta r The thickness of the single grid is the area of the descending ring segment;
the grid marking model of the axial flow type preheater structure in the steam generator is characterized in that after the original steam generator grid is marked, a marking area is converted from a fluid area to a solid area, meanwhile, a water supply inlet at the top of a descending ring section is isolated into two parts by the conversion, as shown in fig. 3, a double-layer sleeve surrounding area is set as a cold side inlet 10, and the rest is a hot side inlet 9; the mesh model of the steam generator with the axial-flow type preheater is built through the steps 2 to 4;
step 5: definition of the drag coefficient of the descending loop section with axial flow preheater structure:
the steam generator numerical model established based on the porous medium model is coarser in grid division, the additional resistance introduced by the axial flow type preheater structure of the descending ring section cannot be reflected, the resistance of the descending ring section is introduced into the model to be realized by empirical calculation relation, and the resistance coefficient is obtained by adopting the existing empirical relation and the existing experimental data analysis;
step 6: and (3) calculating thermal hydraulic parameters of the steam generator with the axial-flow type preheater:
and (3) carrying out thermodynamic and hydraulic numerical calculation on the established grid model with the axial-flow type preheater steam generator based on the computational fluid mechanics model, carrying out error analysis on a numerical calculation result and a test result, when the precision meets the requirement, successfully establishing the grid model with the axial-flow type preheater steam generator, returning to the step (2) when the precision does not meet the requirement, carrying out grid encryption and optimization operation, then continuing the follow-up operation, and repeatedly iterating until the calculation precision requirement is met.
The foregoing description is only one specific embodiment of the present invention, and is not intended to limit the scope of the invention, and all equivalent structures or equivalent processes using the descriptions of the present invention and the accompanying drawings, or direct or indirect application in other related technical fields, are included in the scope of the present invention.

Claims (1)

1. A nuclear power system with axial flow type preheater steam generator operation characteristic analysis method is characterized in that: the method comprises the following steps:
step 1: analyzing the flow heat transfer process inside the steam generator, determining a computational domain and building a geometric model:
the flow process of the secondary side fluid of the steam generator is as follows: the secondary side fluid flows into the descending ring section through the water supply device, and the flowing direction is downward; the annular gap at the bottom of the descending ring section flows into the U-shaped tube bundle area, and the flowing direction is changed to be upward; the secondary side fluid becomes gas-liquid two phases after heat exchange in the U-shaped tube bundle area, and finally enters a steam-water separator; the flow process of the primary side fluid of the steam generator is as follows: fluid flows upwardly through the tube sheet from the inlet lower plenum and is then distributed by the tube sheet to each of the U-tubes on the primary side; the primary side fluid exchanges heat with the secondary side fluid in the process of flowing in the U-shaped pipe, and then flows out after being collected to an outlet cavity through a pipe plate from the outlet end of the U-shaped pipe; thus, the calculation domain for the steam generator is determined as: the secondary side comprises a descending loop section area, a U-shaped tube bundle area and a steam-water separator inlet area, wherein a water supply inlet is arranged at the top of the descending loop section, namely the water level of the steam generator; the primary side comprises an inlet lower chamber, a tube plate, a U-shaped tube bundle area and an outlet lower chamber; then, a geometric modeling software is adopted to build a geometric model for the calculation domain, wherein the modeling of the U-shaped tube bundle area and the tube plate is simplified into an integral inverted U-shaped channel;
step 2: grid division is carried out on the geometric model established in the step 1, a grid model of a steam generator calculation domain is established, the coincidence of a central axis and a z axis of the whole grid is required to be ensured, and the subsequent grid marking is facilitated; the U-shaped tube bundle area and the grid of the tube plate area are processed into a porous medium model;
step 3: analyzing the structure of an axial flow preheater used in a steam generator, determining the implementation method: the main structure of the axial flow type preheater in the steam generator consists of two parts, namely a semi-cylindrical double-layer sleeve arranged on a descending ring section on the cold side of the steam generator and a central baffle arranged at the junction of the cold side and the hot side of a U-shaped tube bundle region of the steam generator; the two-part structure ensures that the secondary side fluid from the descending ring section of the steam generator to the area at the height of the central baffle plate of the U-shaped tube bundle area independently flows and exchanges heat in the cold side area or the hot side area, improves the average heat exchange temperature difference of the first side and the second side, and realizes the enhanced heat transfer; according to the characteristics, solid areas are arranged in the descending ring section area and the central area of the U-shaped tube bundle area of the grid of the steam generator, so that the independent flow heat exchange function of the secondary side fluid in the cold side area or the hot side area of the secondary side fluid is realized;
step 4: the grid marking method realizes the axial flow type preheater structure of the steam generator:
according to the structure of the axial flow type preheater, the grid marking area is provided with a U-shaped tube bundle area and a descending ring section area, which are respectively as follows:
u-shaped tube bundle area central baffle grid marking:
assume that the radius of the U-shaped tube bundle area is R t The bottom plane of the U-shaped tube bundle zone is at z=z 0 Plane, x > 0, is the hot side of the steam generator and vice versa, a thick delta is established in the U-shaped tube bundle region t The central partition board with the height h has a grid marking model as follows:
wherein x, y and z are the coordinate positions of the grids, and care needs to be taken that the thickness of the central baffle is not smaller than the minimum grid size of the area; the grid satisfying the above positional relationship is marked as a central separator;
descending ring section double-layer sleeve grid marking:
assuming that the inner ring radius of the descending ring section is R at different heights id (z) semi-cylindrical double-layer sleeve radius of axial flow preheater is R a (z) establishing a double-layer sleeve structure with the same height as the descending ring section in the descending ring section area, wherein a grid marking model is as follows:
and->
Wherein delta r The thickness of the single grid is the area of the descending ring segment;
the grid marking model of the axial flow type preheater structure in the steam generator is characterized in that after the original steam generator grid is marked, a marking area is converted from a fluid area into a solid area, meanwhile, the conversion enables a water supply inlet at the top of a descending ring section to be separated into two parts, a double-layer sleeve surrounding area is set as a cold side inlet, and the rest part is a hot side inlet; the mesh model of the steam generator with the axial-flow type preheater is built through the steps 2 to 4;
step 5: definition of the drag coefficient of the descending loop section with axial flow preheater structure:
the numerical model of the steam generator established based on the porous medium model is coarser in grid division, and cannot reflect the extra resistance introduced by the axial flow type preheater structure of the descending ring section, and the corresponding resistance coefficient is introduced into the model to realize the effect;
step 6: and (3) calculating thermal hydraulic parameters of the steam generator with the axial-flow type preheater:
and (3) carrying out thermodynamic and hydraulic numerical calculation on the established grid model with the axial-flow type preheater steam generator based on the computational fluid mechanics model, carrying out error analysis on the obtained calculation result and the test result, when the precision meets the requirement, successfully establishing the grid model with the axial-flow type preheater steam generator, and when the precision does not meet the requirement, returning to the step (2), adjusting grids, carrying out grid encryption operation, then continuing the follow-up operation, and repeatedly iterating until the calculation precision requirement is met.
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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108170924A (en) * 2017-12-21 2018-06-15 西安交通大学 One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up
CN112798309A (en) * 2020-12-30 2021-05-14 西安交通大学 Steam generator test device and method simulating presence or absence of axial flow type preheater

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US9175845B2 (en) * 2012-07-10 2015-11-03 Westinghouse Electric Company Llc Axial flow steam generator feedwater dispersion apparatus

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108170924A (en) * 2017-12-21 2018-06-15 西安交通大学 One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up
CN112798309A (en) * 2020-12-30 2021-05-14 西安交通大学 Steam generator test device and method simulating presence or absence of axial flow type preheater

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* Cited by examiner, † Cited by third party
Title
郑恩祖 ; 吕红 ; 罗福红 ; 何世贤 ; .蒸汽发生器管板二次侧表面温度场瞬态计算.核科学与工程.2017,(06),全文. *

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