CN114528734A - Reactor pressure vessel heat insulation layer heat loss evaluation method with water injection cooling system - Google Patents
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Abstract
The invention discloses a method for evaluating heat loss of a heat-insulating layer of a reactor pressure vessel with a water injection cooling system, which comprises the following steps: s1, obtaining the heat conductivity coefficient lambda of the heat preservation layer based on the heat preservation layer sample one-way heat transfer testsAnd qualitative temperature TmThe relationship between; s2, constructing a periodic unit model of the cylinder heat-insulating structure based on the symmetry characteristic of the heat-insulating layer arrangement, and calculating to obtain the thermal state gap leakage flow of the cylinder heat-insulating structure based on the periodic unit model; s3, constructing a full-scale model of the cylinder heat-insulating structure based on the thermal state gap leakage flow constructed and obtained in the step S2, and calculating and obtaining the heat loss of the cylinder heat-insulating structure based on the full-scale model. The evaluation method of the invention takes into accountAnd a large number of seam gaps between the heat insulation layers and the supports are predicted, so that the heat loss of the heat insulation layers with a large number of seam gaps is predicted, and the effectiveness of heat loss evaluation of the heat insulation layers is improved.
Description
Technical Field
The invention relates to the technical field of design of a nuclear power reactor heat-insulating layer, in particular to a method for evaluating heat loss of a reactor pressure vessel heat-insulating layer with a water injection cooling system.
Background
The reactor pressure vessel heat-insulating layer is arranged on the outer side of a Reactor Pressure Vessel (RPV) and contains the whole reactor pressure vessel, and the reactor pressure vessel heat-insulating layer has the main functions of reducing the heat loss of the reactor, reducing the environmental temperature and the temperature difference between the inner wall surface and the outer wall surface of the RPV and ensuring the safe and stable operation of the reactor. Compared with the prior nuclear power technology and the safety characteristic requirement of the third-generation nuclear power technology, in the aspect of dealing with the serious accident of reactor core melting, a reactor cavity water injection cooling system (CIS) needs to be additionally arranged, namely, the heat preservation layer and the RPV outer surface form a specific annular cavity together, cooling water enters the annular cavity from a water injection pipe positioned at the bottom of the heat preservation layer and cools the pressure vessel, so that RPV is prevented from being melted through, and the structural integrity of the reactor pressure vessel is kept. Meanwhile, the structural integrity of the flow channel needs to be kept under the working condition of CIS water injection, so that a lining plate is additionally arranged between the heat-insulating layer and the RPV and is supported and fixed on the pile pit wall through the heat-insulating layer. Due to the presence of the CIS flow channels and the added support, there is an increase in joint gaps between the insulation and the supports and penetrations as compared to previous stacks without CIS.
The heat loss of the insulating layer is generally evaluated by combining a heat transfer test with an empirical formula in the conventional stack type with CIS. The empirical formula method has a single evaluation model, can only do a large amount of simplified processing and conservative analysis on local important structures such as the support of the heat-insulating layer and the joint penetrating through the heat-insulating layer, and is difficult to effectively evaluate the heat loss of the heat-insulating layer when the problems of field installation and debugging such as the gap over-tolerance of the heat-insulating layer and the gap leakage flow occur.
Therefore, an effective analysis method including a large number of insulation layer gaps needs to be established for the insulation layer of the reactor pressure vessel cylinder of the reactor cavity water injection cooling system.
Disclosure of Invention
The invention aims to provide a method for evaluating heat loss of an insulating layer of a reactor pressure vessel with a water injection cooling system, which considers a large number of seam gaps between insulating layers and between the insulating layer and a support and improves the effectiveness of heat loss evaluation of the insulating layer.
The invention is realized by the following technical scheme:
the method for evaluating the heat loss of the heat-insulating layer of the reactor pressure vessel with the water injection cooling system comprises the following steps of:
s1, obtaining the heat conductivity coefficient lambda of the heat preservation layer based on the heat preservation layer sample one-way heat transfer testsAnd qualitative temperature TmThe relation between the two is obtained, namely the heat conductivity coefficients of the heat-insulating layer sample piece at different temperatures are obtained;
s2, constructing a periodic unit model of the cylinder heat-insulating structure based on the symmetry characteristic of the heat-insulating layer arrangement, and calculating to obtain the thermal state gap leakage flow of the cylinder heat-insulating structure based on the periodic unit model;
s3, constructing a full-scale model of the cylinder heat-insulating structure based on the thermal state gap leakage flow constructed and obtained in the step S2, and calculating and obtaining the heat loss of the cylinder heat-insulating structure based on the full-scale model.
The evaluation method of the invention considers a large amount of seam gaps between the heat preservation layers and the supports, predicts the heat loss of the heat preservation layers with a large amount of seam gaps, and improves the effectiveness of heat loss evaluation of the heat preservation layers.
Further, in step S1, a heat insulating layer is obtainedEquivalent coefficient of thermal conductivity lambdasTaking the heat conductivity coefficients of the heat-insulating layers with different thicknesses into consideration, taking the average value of the heat conductivity coefficients with different thicknesses as the final heat conductivity coefficient value, and deducing the heat conductivity coefficient lambda through a polynomial fitting methodsAnd qualitative temperature TmThe relationship between them.
Further, in step S2, when constructing the periodic unit model of the cylinder thermal insulation structure, the gap areas between the thermal insulation blocks of different height layers, the gap areas between the thermal insulation block and the penetrating member, and the gap areas between the thermal insulation block and the support are equivalent to the gap areas at the contact position of the support and the thermal insulation block at the height position according to the principle of equal area.
Further, the equivalent formula corresponding to the principle of equal area is as follows:
Seq＝S1+S2+S3
in the formula, SeqShowing the equivalent clearance area between the heat preservation block and the support; s1Showing the gap area between the heat preservation blocks; s2Showing the clearance area between the heat preservation block and the penetrating piece; s3Showing the clearance area between the insulating block and the support.
According to the invention, all gaps are equivalent to the contact area of the support and the insulating layer through the principle of equal area, grids at the small gaps can be eliminated, and the number of grids can be greatly reduced.
Further, in step S2, when the cylinder heat-insulating structure periodic unit model is constructed, Fluent software is used for convergence solution based on actual working condition parameters and boundary conditions in the heat-insulating structure periodic unit model, so as to obtain the thermal-state gap leakage flow.
Further, the actual condition parameters include the thermal conductivity λ obtained in step S1sAnd physical parameters of air, stainless steel, alloy steel and concrete in the periodic unit model of the heat-insulating structure.
Further, the boundary conditions include an inlet boundary condition and an outlet boundary condition, the inlet boundary condition being an air inlet temperature and a flow rate; the outlet boundary condition is a pressure outlet, and the outer wall surface condition of the pressure container is temperature field setting or heat flux density setting; and the boundary condition of the outer wall of the pile pit concrete is temperature setting.
Further, in step S3, the full-scale model includes a pressure vessel outer wall, a pressure vessel cylinder insulating layer, a pressure vessel support, a main pipeline and a main pipeline insulating layer, concrete, and a fluid region formed by enveloping each part of solid structure and the pressure vessel outer wall.
The heat insulation layer of the pressure container is composed of a plurality of heat insulation blocks, the heat insulation blocks are supported by a supporting structure, the heat insulation layers are embedded into the stainless steel lining, and an annular cavity formed between the stainless steel lining and the pressure container is a cooling flow channel.
Further, in step S3, when constructing the full-scale model of the cylinder insulation structure, a geometric model is constructed first, then the geometric model is converted into a parameter matrix, and when solving, the inlet air volume after the mass source loaded into the fluid domain through the custom function is subtracted from the inlet air volume of the whole heap pit is taken as the finally calculated inlet air volume boundary condition.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. according to the invention, the heat loss of the heat-insulating layer with a large number of seam gaps can be rapidly predicted through the simplified cylinder heat-insulating layer model, and the effectiveness of heat loss evaluation of the heat-insulating layer is improved.
2. According to the invention, all gaps are equivalent to the contact area of the support and the insulating layer through the principle of equal area, grids at the small gaps can be eliminated, and the number of grids can be greatly reduced.
3. The invention represents the whole cylinder heat-insulating layer model by simulating the cylinder heat-insulating layer period unit model, and can reduce the calculation time of the whole model.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a block flow diagram of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1:
as shown in fig. 1, the method for evaluating heat loss of the heat insulating layer of the reactor pressure vessel with the water injection cooling system comprises the following steps:
s1, obtaining the heat conductivity coefficient lambda of the heat preservation layer based on the heat preservation layer sample one-way heat transfer testsAnd qualitative temperature TmThe relationship between the thermal conductivity coefficient of the insulating layer sample piece at different temperatures is obtained:
the heat transfer test was performed according to ASTM C1061, and the thermal conductivity of the insulation samples was measured at different temperatures. The test sample piece can be subjected to certain scaling according to the size of a specific insulating layer, meanwhile, the sample piece needs different thicknesses for researching the heat conductivity coefficients of the insulating layers with different thicknesses, then, the average value of the heat conductivity coefficients with different thicknesses can be taken as the final heat conductivity coefficient value, the relation between the heat conductivity coefficient and the temperature is deduced through a polynomial fitting method (generally, a linear formula), and the physical property parameter setting is provided for the following numerical simulation.
S2, constructing a periodic unit model of the cylinder heat-insulating structure based on the symmetry characteristic of the heat-insulating layer (firstly constructing a geometric model, and then converting the geometric model into a parameter matrix), and calculating to obtain the thermal-state gap leakage rate of the cylinder heat-insulating structure based on the periodic unit model;
and (3) establishing a periodic unit model by considering the structural symmetry of the cylinder heat-insulating layer, wherein if 24 supports are uniformly distributed in a circle of the cylinder heat-insulating layer, the cylinder circumferential 15-degree model is the periodic unit model. The area of investigation is the portion between the RPV outer surface and the pit shield wall. In the case of geometric mesh division, since there are a large number of small gaps between the insulation layers and the through-penetrating members and supports, if the mesh between the gaps is to be completely built, the mesh will be very numerous due to the large difference in size between the gaps and the entire space. In the invention, the clearance area of the heat-insulating blocks of different height layers, the clearance area between the heat-insulating blocks and the penetrating piece and the support are equivalent to the clearance area of the contact part of the support and the heat-insulating blocks at the height position by adopting the equal area principle, and the formula (1) gives the relation:
Seq＝S1+S2+S (1)
in the formula, SeqShowing the equivalent clearance area between the heat preservation block and the support; s1Showing the gap area between the heat preservation blocks; s2Showing the clearance area between the heat preservation block and the penetrating piece; s3Showing the clearance area between the insulating block and the support. The arrangement mode of the steel lining plate is the same as that of the heat-insulating layer, and the clearance area of the lining plate can also be calculated by the formula (1).
By the principle of equivalent area, the mesh division in fine gaps can be avoided, thereby greatly reducing the total mesh number. The model adopts an ANSYS Meshing integrated grid division strategy to generate grids, so that grid nodes of fluid-fluid, fluid-solid and solid-solid contact surfaces are ensured to be completely corresponding, and the continuity of parameters of each node during calculation is ensured.
When defining the boundary conditions, the inlet boundary conditions are air inlet temperature and flow rate; outlet boundary conditions are pressure outlet (typically atmospheric pressure); the RPV outer wall surface condition is temperature field setting or heat flux density setting; the boundary condition of the outer wall of the concrete is temperature setting, and the environmental temperature in the containment is generally taken.
The setting of physical parameters of air, stainless steel, alloy steel, concrete and the like in the model can refer to corresponding physical handbooks; the thermal conductivity of the insulating layer takes the relational expression obtained in step S1). The turbulence model adopts a standard k-epsilon model, and the radiation heat exchange model selects a Surface-to-Surface model. In order to ensure the convergence of the solving process, the flow and heat transfer phenomena (not including radiation heat exchange) in the calculation domain are simulated firstly in the calculation process, and after the calculation result is converged, a radiation heat exchange module is added for calculation until the result is converged.
S3, constructing a full-scale model of the cylinder heat-insulating structure (firstly constructing a geometric model and then converting the geometric model into a parameter matrix) based on the thermal-state clearance leakage flow rate constructed and obtained in the step S2, and calculating and obtaining the heat loss of the cylinder heat-insulating structure based on the full-scale model:
due to the asymmetric arrangement of the ventilation flow passages, an integral model needs to be established. The three-dimensional model comprises an RPV outer wall, an RPV cylinder heat-insulating layer, an RPV support, a main pipeline heat-insulating layer (an inner part of a primary shielding wall), concrete, solid structures of all parts and a fluid domain formed by enveloping the RPV outer wall. The leakage quality, the leakage rate and the leakage temperature of the inner sides of the heat-insulating layers at different heights can be obtained in the step S2, so that when the integral model is established, the leakage quality and the leakage energy of the gaps of the heat-insulating layers at different heights can be set through a user-defined function (UDF), and a corresponding geometric model of the gaps of the heat-insulating layers does not need to be established. The method of adding mass and energy sources in the model can eliminate the gap grids, so that the simulation method is fast and efficient. And in order to ensure that the inlet air volume is consistent with a given working condition, subtracting the inlet air volume loaded to a mass source in a fluid domain through UDF from the whole stack pit inlet air volume to serve as a finally calculated inlet air volume boundary condition. Other boundary conditions, physical property parameters, and solving methods are the same as those in step S2.
Two working conditions were simulated using the above evaluation method, with a 3mm gap working condition I and a 0mm gap working condition II. The results of heat loss and the like are shown in Table 1.
TABLE 1 simulation results under different conditions
| Parameter(s) | Working condition I | Working condition II |
| Inlet temperature (. degree.C.) | 17 | 17 |
| Inlet portAir volume (m)3/h) | 13600 | 13600 |
| Clearance (mm) | 3 | 0 |
| Average temperature (. degree. C.) of concrete | 37.19 | 34.27 |
| Local maximum temperature (. degree. C.) of concrete | 74.62 | 74.02 |
| Average heat loss (W/m) of insulating layer2) | 1321.91 | 86.84 |
| Total heat loss of insulating layer (kW) | 304.04 | 19.97 |
Because the gap exists in the working condition I, the heat loss caused by the working condition I is far larger than that caused by the working condition II, and the results also reflect that the existence of the gap really influences the heat transfer cooling effect, so that the prior empirical formula cannot be adopted simply and the existence of the gap is ignored.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (9)
1. The method for evaluating the heat loss of the heat-insulating layer of the reactor pressure vessel with the water injection cooling system is characterized by comprising the following steps of:
s1, obtaining the heat conductivity coefficient lambda of the heat preservation layer based on the heat preservation layer sample one-way heat transfer testsAnd qualitative temperature TmThe relationship between;
s2, constructing a periodic unit model of the cylinder heat-insulating structure based on the symmetry characteristic of the heat-insulating layer arrangement, and calculating to obtain the thermal state gap leakage flow of the cylinder heat-insulating structure based on the periodic unit model;
s3, constructing a full-scale model of the cylinder heat-insulating structure based on the thermal state gap leakage flow constructed and obtained in the step S2, and calculating and obtaining the heat loss of the cylinder heat-insulating structure based on the full-scale model.
2. The method for evaluating the heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system as claimed in claim 1, wherein in step S1, the equivalent thermal conductivity λ of the thermal insulation layer is obtainedsTaking the heat conductivity coefficients of the heat-insulating layers with different thicknesses into consideration, taking the average value of the heat conductivity coefficients with different thicknesses as the final heat conductivity coefficient value, and deducing the heat conductivity coefficient lambda through a polynomial fitting methodsAnd qualitative temperature TmThe relationship between them.
3. The method for evaluating heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system as claimed in claim 1, wherein in step S2, when constructing the periodic unit model of the cylinder thermal insulation structure, the gap area between the thermal insulation blocks of different height layers, the gap area between the thermal insulation block and the penetrating member, and the gap area between the thermal insulation block and the support are equivalent to the gap area at the contact position of the support and the thermal insulation block at the height position according to the principle of area equality.
4. The method for evaluating the heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system as claimed in claim 3, wherein the equivalent formula corresponding to the area equality principle is as follows:
Seq＝S1+S2+S3
in the formula, SeqShowing the equivalent clearance area between the heat preservation block and the support; s1Showing the gap area between the heat preservation blocks; s2Showing the clearance area between the heat preservation block and the penetrating piece; s3The gap area between the insulating block and the support is shown.
5. The method for evaluating the heat loss of the heat-insulating layer of the reactor pressure vessel with the water injection cooling system according to claim 1, wherein in step S2, when the cylinder heat-insulating structure periodic unit model is constructed, Fluent software is used for convergence solution based on actual working condition parameters and boundary conditions in the heat-insulating structure periodic unit model to obtain the thermal state gap leakage flow.
6. The method for evaluating heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system as recited in claim 5, wherein the physical parameters comprise the thermal conductivity λ obtained in step S1sAnd parameters of air, stainless steel, alloy steel and concrete in the periodic unit model of the heat-insulating structure.
7. The method for assessing heat loss in the thermal insulation layer of the reactor pressure vessel with the water injection cooling system according to claim 5, wherein the boundary conditions comprise an inlet boundary condition and an outlet boundary condition, and the inlet boundary condition comprises an air inlet temperature and an air outlet flow; the outlet boundary condition is a pressure outlet, and the outer wall surface condition of the pressure container is temperature field setting or heat flux density setting; and the boundary condition of the outer wall of the pile pit concrete is temperature setting.
8. The method for evaluating heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system according to claim 1, wherein in step S3, the full-scale model comprises an outer wall of the pressure vessel, an insulation layer of a cylinder of the pressure vessel, a support of the pressure vessel, a main pipeline, an insulation layer of the main pipeline, concrete, and a fluid region formed by enveloping solid structures of all parts and the outer wall of the pressure vessel.
9. The method for evaluating the heat loss of the thermal insulation layer of the reactor pressure vessel with the water injection cooling system according to claim 1, wherein in the step S3, when a full-size model of the cylinder thermal insulation structure is constructed, a geometric model is constructed, then the geometric model is converted into a parameter matrix, and when solving, the inlet air volume after the mass source loaded into the fluid domain through a custom function is subtracted from the inlet air volume of the whole stack pit to be used as a finally calculated inlet air volume boundary strip.
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107633889A (en) * | 2017-08-23 | 2018-01-26 | 福建福清核电有限公司 | A kind of method of the imperial No.1 Reactor cavity flooding cooling system validity independent evaluations of China |
| CN110362918A (en) * | 2019-07-12 | 2019-10-22 | 西安交通大学 | A kind of condensation of pressurized water reactor containment two sides and evaporation coupling calculation |
| CN110532586A (en) * | 2019-07-08 | 2019-12-03 | 华北电力大学 | A kind of the subregion decoupling modeling and overall coupling calculation of sodium-cooled fast reactor container |
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107633889A (en) * | 2017-08-23 | 2018-01-26 | 福建福清核电有限公司 | A kind of method of the imperial No.1 Reactor cavity flooding cooling system validity independent evaluations of China |
| CN110532586A (en) * | 2019-07-08 | 2019-12-03 | 华北电力大学 | A kind of the subregion decoupling modeling and overall coupling calculation of sodium-cooled fast reactor container |
| CN110362918A (en) * | 2019-07-12 | 2019-10-22 | 西安交通大学 | A kind of condensation of pressurized water reactor containment two sides and evaporation coupling calculation |
Non-Patent Citations (1)
| Title |
|---|
| 张亚斌等: "反应堆压力容器筒体保温层结构间隙对保温效果的影响分析", 《科技视界》, vol. 2020, no. 15, pages 106 - 112 * |
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