CN113643830A - Method for processing core of heat pipe cooling reactor - Google Patents
Method for processing core of heat pipe cooling reactor Download PDFInfo
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- CN113643830A CN113643830A CN202110913108.XA CN202110913108A CN113643830A CN 113643830 A CN113643830 A CN 113643830A CN 202110913108 A CN202110913108 A CN 202110913108A CN 113643830 A CN113643830 A CN 113643830A
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- powder
- heat pipe
- heat
- matrix
- reactor core
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- 238000000034 method Methods 0.000 title claims abstract description 23
- 238000001816 cooling Methods 0.000 title claims abstract description 14
- 238000012545 processing Methods 0.000 title claims abstract description 9
- 239000000843 powder Substances 0.000 claims abstract description 74
- 239000011159 matrix material Substances 0.000 claims abstract description 25
- 239000000446 fuel Substances 0.000 claims abstract description 13
- 238000010438 heat treatment Methods 0.000 claims description 32
- 239000002245 particle Substances 0.000 claims description 19
- 229910001220 stainless steel Inorganic materials 0.000 claims description 18
- 239000010935 stainless steel Substances 0.000 claims description 18
- 238000004519 manufacturing process Methods 0.000 claims description 6
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical group [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 5
- 230000005484 gravity Effects 0.000 claims description 4
- 229910002804 graphite Inorganic materials 0.000 claims description 3
- 239000010439 graphite Substances 0.000 claims description 3
- 229910052751 metal Inorganic materials 0.000 claims description 3
- 239000002184 metal Substances 0.000 claims description 3
- 238000012546 transfer Methods 0.000 abstract description 10
- 239000000758 substrate Substances 0.000 description 7
- 238000012360 testing method Methods 0.000 description 7
- 238000002474 experimental method Methods 0.000 description 6
- 239000001307 helium Substances 0.000 description 5
- 229910052734 helium Inorganic materials 0.000 description 5
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 5
- 238000003672 processing method Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000000704 physical effect Effects 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 229920000742 Cotton Polymers 0.000 description 1
- YKTSYUJCYHOUJP-UHFFFAOYSA-N [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] Chemical compound [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] YKTSYUJCYHOUJP-UHFFFAOYSA-N 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 238000003754 machining Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
- G21C5/16—Shape of its constituent parts
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Investigating Or Analyzing Materials Using Thermal Means (AREA)
Abstract
The invention discloses a method for processing a reactor core of a heat pipe cooling reactor, and relates to the technical field of heat pipe cooling reactors. According to the invention, the powder is filled between the fuel rod and the matrix, and between the heat pipe and the matrix, so that the heat transfer efficiency is improved; the powder filling gap has a high effective heat conductivity coefficient, so that the temperature difference between the reactor core matrix and the heat pipe can be reduced, and the safety allowance of the reactor is improved; the filled powder has fluidity, can effectively absorb the thermal expansion of the core matrix and the heat pipe, and reduces the contact stress of the core matrix and the heat pipe.
Description
Technical Field
The invention relates to the technical field of heat pipe cooling reactors, in particular to a method for processing a reactor core of a heat pipe cooling reactor.
Background
The heat pipe cooling reactor uses a solid core, and the fuel rods and the heat pipes are sequentially assembled in the solid matrix, so that assembly gaps inevitably exist among the heat pipes, the fuel rods and the matrix, and the specific structure is shown in figure 1.
When the reactor operates, heat is generated from the fuel rods and is transferred to the heat pipe through the assembly gap and the base body, and the heat pipe transfers the heat to the thermoelectric conversion system, so that the conversion from heat energy to electric energy is completed. In the prior art, most assembly gaps are in a vacuum environment, and when contact between structures is not generated, heat transfer depends on heat radiation, so that great thermal resistance exists, the temperature difference between a fuel rod and a heat pipe is too large, and the safety allowance of a reactor is reduced. If the size of the assembly gap is reduced, the thermal resistance between assemblies can be reduced to a certain extent because the structures are easier to contact; however, under the expected transient operating conditions of the reactor, the core matrix or the heat pipe is thermally expanded, which easily causes excessive contact stress between the matrix and the heat pipe, thereby causing the safety problem of the reactor.
Therefore, those skilled in the art are dedicated to provide a method for processing a core of a heat pipe cooled reactor, which can reduce the thermal resistance of heat transfer of the core of the heat pipe cooled reactor, and can avoid excessive contact stress between the core substrate and the heat pipe.
Disclosure of Invention
In view of the defects in the prior art, the technical problem to be solved by the present invention is how to provide a method for processing a core of a heat pipe cooled reactor, which reduces the thermal resistance of the heat transfer of the core of the heat pipe cooled reactor and avoids the generation of an excessive contact stress between the core substrate and the heat pipe.
In order to achieve the above object, the present invention provides a method for manufacturing a core of a heat pipe cooled reactor, in which fuel rods and heat pipes are sequentially assembled in a matrix, characterized in that powder is filled between the fuel rods and the matrix and between the heat pipes and the matrix.
Further, the powder is filled by gravity, i.e. the powder is filled by self-flowing means.
Preferably, the material of the powder is metal, especially stainless steel.
Preferably, the material of the powder is graphite.
Preferably, the particle size of the powder does not exceed 200 μm.
Further, the particle size of the powder is not less than 10 μm.
Preferably, the powder is spherical.
The invention provides a method for determining the flowability of powder, which comprises the steps of containing the powder in a standard funnel and testing the time for which the powder flows through the standard funnel by means of the self weight.
The invention provides a method for measuring the heat conductivity coefficient of powder, which comprises the steps of arranging a stainless steel cylinder and a heating rod, wherein the heating rod is arranged at the center of the stainless steel cylinder, powder is filled between the heating rod and the stainless steel cylinder, and thermocouples are arranged on the outer walls of the heating rod and the stainless steel cylinder; the thermal conductivity of the powder was calculated from the heating power of the heating rod and the temperature measured by the thermocouple.
The invention also provides a heat pipe cooling reactor core, which is processed by the processing method of the heat pipe cooling reactor core, and the heat pipe cooling reactor core is filled with powder between the fuel rod and the substrate and between the heat pipe and the substrate in a self-flowing mode.
The invention has at least the following beneficial technical effects:
1. the processing method of the reactor core of the heat pipe cooling reactor provided by the invention is characterized in that powder is filled in gaps between the fuel rod and the matrix and between the heat pipe and the matrix, and the gaps filled with the powder have higher heat transfer efficiency than vacuum gaps; the powder fills the higher effective heat conductivity coefficient of the clearance, can reduce the temperature difference between the reactor core matrix and the heat pipe, improve the safety allowance of the reactor.
2. According to the processing method of the reactor core of the heat pipe cooling reactor, the filled powder has fluidity, the thermal expansion of the reactor core matrix and the heat pipe can be effectively absorbed, and the contact stress of the reactor core matrix and the heat pipe is reduced.
3. The processing method of the reactor core of the heat pipe cooling reactor provided by the invention can properly increase the assembly clearance between the reactor core substrate and the heat pipe, thereby reducing the machining difficulty and the assembly difficulty.
The conception, the specific structure and the technical effects of the present invention will be further described with reference to the accompanying drawings to fully understand the objects, the features and the effects of the present invention.
Drawings
FIG. 1 is a schematic view of a prior art heat pipe cooled reactor core;
FIG. 2 is a schematic view of a heat pipe cooled reactor core according to a preferred embodiment of the present invention;
FIG. 3A is a schematic view of a powder flowability testing device according to a preferred embodiment of the present invention;
FIG. 3B is a standard hopper of the powder flowability test apparatus according to the preferred embodiment of the present invention;
FIG. 4A is a flow chart of a powder thermal conductivity testing apparatus according to a preferred embodiment of the present invention;
FIG. 4B is a schematic diagram of a powder thermal conductivity testing apparatus according to a preferred embodiment of the present invention;
FIG. 5A is a graph showing the thermal conductivity of the powder in an air environment according to a preferred embodiment of the present invention;
FIG. 5B is a graph of the thermal conductivity of the powder in a helium environment in accordance with a preferred embodiment of the present invention.
Detailed Description
The technical contents of the preferred embodiments of the present invention will be more clearly and easily understood by referring to the drawings attached to the specification. The present invention may be embodied in many different forms of embodiments and the scope of the invention is not limited to the embodiments set forth herein.
In the drawings, structurally identical elements are represented by like reference numerals, and structurally or functionally similar elements are represented by like reference numerals throughout the several views. The size and thickness of each component shown in the drawings are arbitrarily illustrated, and the present invention is not limited to the size and thickness of each component. The thickness of the components may be exaggerated where appropriate in the figures to improve clarity.
As shown in fig. 1, in the conventional heat pipe-cooled reactor core, there are gaps between the fuel rods and the substrate and between the heat pipes and the substrate. As shown in fig. 2, in the method for processing a core of a heat pipe cooled reactor according to the present invention, powder is filled in the gap between the fuel rod and the matrix and the gap between the heat pipe and the matrix, and the powder is filled by gravity.
In the present invention, the powder is filled by gravity, i.e. the powder is filled by self-flow.
In order to meet the requirements of thermal expansion absorption and clearance heat transfer enhancement at the same time, the filling powder has good fluidity, and when the clearance is narrowed due to the thermal expansion of the core matrix and the heat pipe, the filling powder can absorb the expansion, so that the core matrix and the heat pipe are prevented from contacting and generating stress. Meanwhile, the gaps filled with the powder have good heat transfer performance, namely the effective heat conductivity coefficient is high, so that the heat of the reactor core matrix can be effectively transferred to the heat pipe.
Therefore, the powder material of the invention can be graphite and metal, especially stainless steel; the particle size range of the powder is 10-200 mu m; the powder is spherical in shape.
As shown in fig. 3A and 3B, the present invention measured the flowability of graphite powder and stainless steel powder of different particle sizes by the funnel method, and the powder flowability was expressed as the time for which the powder flowed through a standard funnel by its own weight. The powder particle size distribution and the micro morphology are analyzed through a laser particle size analyzer and a scanning electron microscope, and the relationship between the powder flowability and the particle size distribution and the micro morphology is obtained.
The relationship between the three statistical particle sizes and the flowability of the powder obtained by analysis of the laser particle size analyzer is as follows: the larger the difference between the statistical particle sizes is, the larger the deviation sphericity of the powder is, and the poorer the fluidity is; the smaller the particle size of the powder, the poorer the flowability; the smoother the microscopic morphology obtained by the scanning electron microscope, the poorer the fluidity. The three statistical particle sizes are respectively: volume average particle diameter, area average particle diameter, number average particle diameter.
As shown in fig. 4A and 4B, by using a radial heat flow method and an effective thermal conductivity testing system, effective filling thermal conductivity coefficients of graphite powder and stainless steel powder with different particle sizes in an air and helium environment are obtained, and further, relationships between the effective filling thermal conductivity coefficient of the powder and physical properties of the powder, physical properties of ambient gas and a powder filling state are determined.
In the measurement of the radial heat flow method, a stainless steel cylinder and a heating rod are arranged, the heating rod is arranged at the center of the stainless steel cylinder, powder is filled between the heating rod and the stainless steel cylinder, and thermocouples are arranged on the outer walls of the heating rod and the stainless steel cylinder; the thermal conductivity of the powder was calculated from the heating power of the heating rod and the temperature measured by the thermocouple.
According to the effective heat conductivity coefficient test result, three main heat transfer paths of solid heat conduction, contact heat conduction and radiation heat transfer exist in the powder filling gap, so that the following change rule of the heat conductivity coefficient is obtained: the higher the thermal conductivity of the ambient gas, the higher the effective thermal conductivity of the powder-filled gap; the stronger the powder flowability, the lower the porosity of the powder-filled gap, and the higher the effective thermal conductivity.
Fig. 5A and 5B show the relationship between the effective thermal conductivity of stainless steel powder and the particle size of the powder in an air environment and a helium environment, respectively.
Example 1
In this example, the flowability of the powder is expressed in terms of the time required for 50g of the powder to flow through a standard funnel by its own weight, and the shorter the time, the better the flowability is.
The equivalent thermal conductivity of the powder was measured by the radial heat flow method. The experimental section of the radial heat flow method mainly comprises a stainless steel cylinder and a heating rod, wherein the wall thickness of the cylinder is 2mm, and the outer diameter of the cylinder is 80 mm; the heating length of the heating rod is 600mm, the diameter of the heating rod is 20mm, and the length-diameter ratio of the heating section is 30: 1. In order to ensure the axial uniformity of the power of the heating rod, the heating wires are uniformly wound on the heating rod. Two ends of the experimental section comprise three layers of aluminum silicate heat insulation cotton to reduce axial heat loss, so that the central area of the experimental section approximately achieves one-dimensional radial heat conduction. The experimental section cylinder wall adopts a thinner heat-insulating layer, so that the heating power and the temperature difference are balanced, and meanwhile, the heat exchange nonuniformity in the axial direction can be reduced. Nine K-type thermocouples are uniformly arranged along the heating rod and the outer wall of the cylinder, wherein the thermocouples on the cylinder wall are arranged outside the experimental section, the thermocouples on the heating rod are buried under the surface of the heating rod, and the lead is led out through one end of the inner side of the heating rod, so that the problem of air tightness caused by leading out of the thermocouple lead from the outer side of the heating rod can be avoided.
When the experiment is carried out under helium filling, firstly, the system pressure is pumped to about 10kPa through a vacuum pump, then, helium is injected until the pressure is slightly higher than one atmosphere, and after the gas is repeatedly pumped and injected for 5 times, each valve is closed, the tightness of the experiment section is kept, and the subsequent experiment is carried out. It should be noted that, because the experiment section raises the temperature, the internal pressure can be increased, so the system needs to be decompressed in the experiment process, and when the temperature reaches the stable temperature each time, the pressure is stabilized near the set pressure point.
The foregoing detailed description of the preferred embodiments of the invention has been presented. It should be understood that numerous modifications and variations could be devised by those skilled in the art in light of the present teachings without departing from the inventive concepts. Therefore, the technical solutions available to those skilled in the art through logic analysis, reasoning and limited experiments based on the prior art according to the concept of the present invention should be within the scope of protection defined by the claims.
Claims (10)
1. A method for manufacturing a core of a heat pipe cooling reactor, in which method fuel rods and heat pipes are assembled in sequence in a matrix, characterized in that powder is filled between the fuel rods and the matrix and between the heat pipes and the matrix.
2. A method of manufacturing a heat pipe cooled reactor core as claimed in claim 1, wherein the powder is gravity filled.
3. A method of manufacturing a heat pipe cooled reactor core as claimed in claim 1, wherein the powder is made of metal.
4. A method of manufacturing a heat pipe cooled reactor core as claimed in claim 1, wherein the powder is graphite.
5. A method of heat pipe cooled reactor core processing as claimed in claim 1, wherein the powder has a particle size of no more than 200 μm.
6. A method of heat pipe cooled reactor core processing as claimed in claim 5, wherein the powder has a particle size of not less than 10 μm.
7. A method of manufacturing a heat pipe cooled reactor core as claimed in claim 1, wherein said powder is spherical.
8. A method for measuring the flowability of a powder according to claim 1, wherein the powder is contained in a standard funnel and the time for which the powder flows through the standard funnel by its own weight is measured.
9. The method for measuring the thermal conductivity of the powder according to claim 1, wherein a stainless steel cylinder and a heating rod are provided, the heating rod is disposed at the center of the stainless steel cylinder, the powder is filled between the heating rod and the stainless steel cylinder, and a thermocouple is provided on the outer wall of the heating rod and the stainless steel cylinder; the thermal conductivity of the powder was calculated from the heating power of the heating rod and the temperature measured by the thermocouple.
10. A heat pipe cooled reactor core manufactured according to the method of any one of claims 1 to 7.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110913108.XA CN113643830A (en) | 2021-08-10 | 2021-08-10 | Method for processing core of heat pipe cooling reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202110913108.XA CN113643830A (en) | 2021-08-10 | 2021-08-10 | Method for processing core of heat pipe cooling reactor |
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| CN113643830A true CN113643830A (en) | 2021-11-12 |
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| CN202110913108.XA Pending CN113643830A (en) | 2021-08-10 | 2021-08-10 | Method for processing core of heat pipe cooling reactor |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110961646A (en) * | 2019-11-07 | 2020-04-07 | 深圳航科新材料有限公司 | Metal powder and method for producing same |
| CN111081398A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Integrated fast spectrum reactor core structure for gapless solid heat transfer |
| CN112102972A (en) * | 2020-08-24 | 2020-12-18 | 中国原子能科学研究院 | Reactor core heat transfer scheme for high-power heat pipe reactor |
| CN112199811A (en) * | 2020-08-10 | 2021-01-08 | 上海交通大学 | Reactor core parameter determination method and device for nuclear thermal propulsion reactor |
| CN112768096A (en) * | 2020-12-31 | 2021-05-07 | 中广核研究院有限公司 | Nuclear power supply device |
-
2021
- 2021-08-10 CN CN202110913108.XA patent/CN113643830A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110961646A (en) * | 2019-11-07 | 2020-04-07 | 深圳航科新材料有限公司 | Metal powder and method for producing same |
| CN111081398A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Integrated fast spectrum reactor core structure for gapless solid heat transfer |
| CN112199811A (en) * | 2020-08-10 | 2021-01-08 | 上海交通大学 | Reactor core parameter determination method and device for nuclear thermal propulsion reactor |
| CN112102972A (en) * | 2020-08-24 | 2020-12-18 | 中国原子能科学研究院 | Reactor core heat transfer scheme for high-power heat pipe reactor |
| CN112768096A (en) * | 2020-12-31 | 2021-05-07 | 中广核研究院有限公司 | Nuclear power supply device |
Non-Patent Citations (3)
| Title |
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| 傅晟威;周;许志红;杨燕华;: "超临界水堆滑压启堆工况下堆芯热工水力动态模拟", 核动力工程, no. 05, pages 69 - 74 * |
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