CN220672227U - Sodium heat pipe cooling reactor core - Google Patents
Sodium heat pipe cooling reactor core Download PDFInfo
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- CN220672227U CN220672227U CN202321858496.7U CN202321858496U CN220672227U CN 220672227 U CN220672227 U CN 220672227U CN 202321858496 U CN202321858496 U CN 202321858496U CN 220672227 U CN220672227 U CN 220672227U
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- core
- heat pipe
- reactor
- reflecting layer
- sodium heat
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- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 title claims abstract description 27
- 229910052708 sodium Inorganic materials 0.000 title claims abstract description 27
- 239000011734 sodium Substances 0.000 title claims abstract description 27
- 238000001816 cooling Methods 0.000 title claims abstract description 11
- 239000000446 fuel Substances 0.000 claims abstract description 30
- 239000011159 matrix material Substances 0.000 claims abstract description 8
- 239000000463 material Substances 0.000 claims description 24
- 229910000691 Re alloy Inorganic materials 0.000 claims description 17
- YUSUJSHEOICGOO-UHFFFAOYSA-N molybdenum rhenium Chemical compound [Mo].[Mo].[Re].[Re].[Re] YUSUJSHEOICGOO-UHFFFAOYSA-N 0.000 claims description 14
- 238000005253 cladding Methods 0.000 claims description 4
- 229910052751 metal Inorganic materials 0.000 claims description 4
- 239000002184 metal Substances 0.000 claims description 4
- 239000008188 pellet Substances 0.000 claims description 3
- 239000012530 fluid Substances 0.000 claims description 2
- 239000010935 stainless steel Substances 0.000 claims description 2
- 229910001220 stainless steel Inorganic materials 0.000 claims description 2
- 239000000758 substrate Substances 0.000 claims 1
- 238000013461 design Methods 0.000 description 12
- 238000010521 absorption reaction Methods 0.000 description 8
- 230000008859 change Effects 0.000 description 8
- 238000010586 diagram Methods 0.000 description 7
- 230000000694 effects Effects 0.000 description 7
- 238000012546 transfer Methods 0.000 description 7
- WUAPFZMCVAUBPE-UHFFFAOYSA-N rhenium atom Chemical compound [Re] WUAPFZMCVAUBPE-UHFFFAOYSA-N 0.000 description 4
- 238000000034 method Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 229910001182 Mo alloy Inorganic materials 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 2
- 239000011358 absorbing material Substances 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 239000011133 lead Substances 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 229910052702 rhenium Inorganic materials 0.000 description 2
- 238000005245 sintering Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 1
- 229910052783 alkali metal Inorganic materials 0.000 description 1
- 150000001340 alkali metals Chemical class 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000008595 infiltration Effects 0.000 description 1
- 238000001764 infiltration Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 229910052750 molybdenum Inorganic materials 0.000 description 1
- 239000011733 molybdenum Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 229910052700 potassium Inorganic materials 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 239000006104 solid solution Substances 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 230000003595 spectral effect Effects 0.000 description 1
- 230000003313 weakening effect Effects 0.000 description 1
- 239000012224 working solution Substances 0.000 description 1
Classifications
-
- 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
Abstract
The application relates to a sodium heat pipe cooling reactor core, its structure includes from inside to outside in proper order: the reactor comprises a reactor core active area, a reflecting layer, a control drum area and a shielding layer; the core active region includes: fuel rods and sodium heat pipes. The fuel rods and the heat pipes are arranged in a triangle and are wrapped by the regular hexagonal prism matrix; the reflecting layer radially surrounds the regular hexagonal prism matrix; the reflecting layer comprises a radial reflecting layer and an axial reflecting layer; the control drum zone comprises 6 control drums; adjacent control drums are radially angled at 60 degrees and are uniformly distributed within the radial reflective layer. The sodium heat pipe cooled reactor core of the present application can remain at full power operation for five years.
Description
Technical Field
The application relates to the technical field of reactor core design, in particular to a sodium heat pipe cooling reactor core.
Background
The inter-nuclear reactor power supply is used as a main power supply for the spacecraft in space to run, has the advantages of small occupied space, long service life, small mass and the like, and the heat pipe cooling reactor is commonly used as a space reactor power supply. The current research results on sodium heat pipe cooled reactors are not much, and because sodium heat pipes are not used in heat pipe cooled reactors, and many aspects of analysis on the physical properties of sodium heat pipe reactor systems are lacking, many research directions can be continued in this respect. Sodium heat pipe cooled reactors have significant differences from common reactors such as pressurized water reactors, gas cooled reactors, etc. in many aspects such as core layout, working medium, materials selection, operating temperature, etc. Therefore, the reactor core physical design analysis work of the sodium heat pipe cooling reactor is carried out, so that the practical application of the sodium heat pipe cooling reactor in the future is possible.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a sodium heat pipe cooling reactor core.
The sodium heat pipe cooling reactor core includes successively from inside to outside:
the reactor comprises a reactor core active area, a radial reflecting layer, a control drum area and a shielding layer;
the core active region includes: fuel rods and sodium heat pipes. The fuel rods and the heat pipes are arranged in a triangle and are wrapped by the regular hexagonal prism matrix;
the radial reflecting layer radially surrounds the regular hexagonal prism matrix;
the control drum zone comprises 6 control drums; adjacent control drums are radially angled at 60 degrees and are uniformly distributed within the radial reflective layer.
Drawings
FIG. 1 is a schematic diagram of a sodium heat pipe structure;
FIG. 2 is a Keff comparison of different wall materials;
FIG. 3 is a schematic view of 15 N and 14 a neutron capture absorption cross-section line diagram of N;
FIG. 4 shows different enrichment levels 15 A Keff result line diagram corresponding to N;
FIG. 5 shows a different embodiment 10 Keff contrast plot of B enrichment;
FIG. 6 is a core model diagram; wherein FIG. 6 (a) is a top view of the core and FIG. 6 (b) is a side view of the core;
FIG. 7 is a point of the heat pipe in the core and its corresponding Keff; where fig. 7 (a) is the point of the heat pipe taken in the core, and fig. 7 (b) is Keff where the heat pipe is placed at different points.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.
The sodium heat pipe cooling reactor core includes successively from inside to outside:
the reactor comprises a reactor core active area, a radial reflecting layer, a control drum area and a shielding layer.
The core active region includes: fuel rods and sodium heat pipes. The fuel rods and the heat pipes are arranged in a triangle and are wrapped by the regular hexagonal prism matrix.
The radial reflecting layer radially surrounds the regular hexagonal prism matrix;
the control drum zone comprises 6 control drums; adjacent control drums are radially angled at 60 degrees and are uniformly distributed within the radial reflective layer.
The region of the core where the fuel elements and heat pipes are stored is called the core active region, where the reactor chain reaction and heat transfer processes take place. Compared with other arrangement modes, the triangle arrangement mode is more compact, the number of the heat pipes is more, the reactor core structure is more compact, the heat transfer efficiency of the tube bundle is higher, and the heat transfer effect of the reactor core is better.
The neutron reflecting layer of the reflecting region can reduce the leakage of neutrons in the core, so that the critical dimension of the core is small when no reflecting layer exists, and a part of fuel can be saved, thereby improving the average output power of the reactor.
The nuclear reactor shielding layer is made of metal material with certain thickness to surround the periphery of the reactor for blocking or weakening various rays emitted by the reactor. Among the various rays, neutrons are extremely harmful to the human body, so the shielding design is mainly used for reducing the percentage or probability of neutron penetration shielding, and has important significance for the safe operation of the reactor.
The control drum performs reactivity control by changing the position of the neutron absorber on the drum body, the main material is generally consistent with the material of the reflecting layer, and the main material is arranged in the radial reflecting layer, so that the size and the quality of the reflecting layer are not increased, and the disturbance on the axial power distribution of the reactor core is small.
In one embodiment, the sodium heat pipe consists of a pipe shell, a working medium and a pipe core; the tube core is a silk-screen tube core; the material of the tube shell is molybdenum-rhenium alloy.
The tube core can be made of 800-mesh stainless steel metal micro-grain net, and the molybdenum-rhenium alloy can be made of Mo-14% Re alloy. As shown in fig. 1, a schematic diagram of the sodium heat pipe structure is provided. As shown in table 1, the design parameters for the sodium heat pipe are provided.
Table 1 design parameters of sodium heat pipe
The tube core of the heat tube mainly has three structures, namely, a groove is formed in the inner wall of the tube, a very thin groove is formed in the inner wall of the tube to increase a capillary tube, the capillary force of the structure is very small, the capillary force is insufficient, the liquid backflow is slower, and the limit heat transfer power (Qmax) of the structure is influenced, so that the heat tube with the structure is less in current application. Another construction is of the wire mesh type, which resembles a towel, and the well known slow towel is wetted by placing one end of the dry towel in water, the wire mesh being a concept which is evident in that the net-like construction produces a greater force of attraction than the grooved, and thus better performance, heat pipes. The internal structure is a sintering structure, the structure of the sintering structure is that metal powder is sintered into a compact metal sponge structure, the infiltration rate of working solution in the heat pipe is higher, and the heat transfer capacity of the heat pipe is higher. Based on comprehensive consideration of various aspects such as performance, design difficulty and cost, the heat pipe capillary structure of the scheme selects a silk screen type tube core.
In selecting the material of the heat pipe wall, a number of factors are considered, including the operating temperature of the pipe, the radiation resistance, the liquid metal corrosion resistance, etc. The compatibility of the heat pipe means that the working fluid in the heat pipe and the shell do not have obvious chemical reaction or physical change or have change but not enough change to influence the working performance of the heat pipe in the expected design life, and the compatibility has important significance in the application of the heat pipe. Only a heat pipe with good long-term compatibility can ensure stable heat transfer performance, long working life and possibility of industrial application. The molybdenum-rhenium alloy is a binary solid solution alloy formed by adding element rhenium into metallic molybdenum, and the unique rhenium effect of the rhenium element ensures that the molybdenum-rhenium alloy has excellent high-temperature mechanical properties of the molybdenum alloy and also has good low-temperature processability which other molybdenum alloys do not have. Meanwhile, the molybdenum-rhenium alloy has good compatibility with nuclear fuels such as UO2, UN, UC and the like, heat pipe heat transfer working media such as alkali metals Li, na, K and the like at high temperature, and rhenium element is a better spectral shift absorber material, so that the critical risk of a reactor in accident can be effectively reduced, and the molybdenum-rhenium alloy becomes a design material for a plurality of heat pipe reactors at home and abroad, especially for a reactor core of a high-temperature space heat pipe reactor. The method includes the steps that the influence of molybdenum-rhenium alloy, lead and steel on the performance of a reactor core is discussed by taking the molybdenum-rhenium alloy, lead and steel as pipe wall materials of the heat pipe respectively, firstly, corresponding input formats of different materials in an MCNP program are searched, the pipe wall material part of a data card in the program is modified, the MCNP program is operated after the corresponding program is modified, and an output file of the MCNP program is opened to find a corresponding Keff result. After the corresponding results are arranged and counted, the corresponding results are outputStatistics are carried out and shown in FIG. 2, wherein each material corresponds to a bar graph, and the left side is B 4 C is all inward, the right side is B 4 C is all outward.
In one embodiment, the fuel rod includes a cylindrical fuel pellet and a tubular cladding.
The material of the fuel pellet is UN fuel; wherein the method comprises the steps of 235 The enrichment degree of U is 80%, and N element is selected 14 N; the material of the cladding is molybdenum-rhenium alloy.
The fuel rod adopts UN fuel, and the U element is mainly dependent on 235 The U fission generates neutrons and energy, which are then chain reacted with un-fissile U elements. Since the N element in UN fuel also has neutron absorption capability, the N element duty ratio in the fuel can also have a certain effect on core performance. N element presence in fuel 14 N and 15 n two natural stable isotopes having different neutron capture capacities due to different neutron absorption cross-sectional sizes. Because of 15 The neutron absorption cross section of N is much smaller than 14 N is increased 15 The ratio of N in the fuel N element may improve core performance. By changing 15 The ratio of N in the element N of the fuel shows the influence of the change of the N on the performance of the reactor core through the change of Keff and is summarized in records:
searching for two isotopes of N 15 N and 14 n neutron capture absorption section data, and importing the corresponding N element radiation capture section data into origin drawing software to obtain 15 N and 14 n, as shown in fig. 3. By changing the UN fuel 15 The concentration of N in N element is observed to influence the reactor core. First find 15 N and 14 n is input format corresponding to MCNP program, the fuel part of data card is modified in the program, and the modification is carried out before 15 The duty ratio conditions of N elements under different enrichment degrees are listed, the MCNP program is operated after the corresponding program is modified, and an output file of the MCNP program is opened to find out a corresponding Keff result. After the corresponding results are arranged and counted, the output is counted to make different enrichmentsDegree of 15 N corresponds to a Keff result line diagram, as shown in FIG. 4, wherein the design requires that the reactor core has sufficient shutdown depth, and Keff is less than or equal to 0.98 under the condition that the control drum is fully inward.
By analyzing the results of core Keff, an improvement can be seen 15 The ratio of N to N element in the fuel can improve the core performance in a small part, but at the same time, the shutdown depth is reduced, and at the same time, because 15 The purification cost of N is higher than 14 N, and the purification difficulty is higher than 14 N, the final choice of core design herein, for economic and materials impact considerations 14 N。
In one embodiment, the material of the reflective layer is BeO.
In one embodiment, each control drum is comprised of 1/6 neutron absorbing material with 5/6 reflecting material; neutron absorbing material B 4 C, performing operation; wherein B is 4 In C 10 The enrichment degree of the B element is 1. The reflective material is BeO.
Select B 4 C is used as a control material for a reactor control drum zone because of its relatively large neutron absorption cross section, B 4 The B element in C being present 10B And (3) with 11 B two natural stable isotopes having different neutron capture capacities due to different neutron absorption cross-sectional sizes. Because of 10 B neutron absorption cross section is less than 11 B, so improve 10 The duty ratio of B in the B element of the fuel can improve the value of the rotary drum. By changing 10 B is B at 4 The effect of the change in the C element on core performance is shown by the change in Keff and summarized in records:
by changing in B4C 11 The degree of enrichment of B in the B element is observed to influence the core. Firstly, searching corresponding input formats of 10B and 11B in an MCNP program, modifying a fuel part of a data card in the program, before modification, listing the duty ratio conditions of the 11B in B elements under different enrichment degrees, operating the MCNP program after modifying the corresponding program, and opening an output file of the MCNP program to find a corresponding Keff result. After the corresponding results are arranged and counted, the output is counted and madeTable 2, fig. 5.
TABLE 2 different 10 Keff of B enrichment
In one embodiment, the material of the shielding region is a molybdenum-rhenium alloy. Specifically, mo-14% Re alloy can be selected.
In one embodiment, the core active region includes: 90 fuel rods and 37 sodium heat pipes.
As shown in table 3, specific design parameters of the core structure are provided.
TABLE 3 specific design parameters of core Structure
As shown in fig. 6, a core model diagram is provided, wherein fig. 6 (a) is a top view of the core and fig. 6 (b) is a side view of the core.
The placement of the heat pipes in the core also has a certain effect on the performance of the core, and the effect of one heat pipe on the core at different positions in the core is studied. And changing the cell card of the reactor core in the MCNP program, and then selecting seven heat pipe points to change. (1) The points (7) respectively correspond to the points which form 85 degrees, 80 degrees, 75 degrees, 60 degrees, 45 degrees, 25 degrees and 10 degrees with the center when the left lower corner of the matrix hexagon is taken as the center of the X\Y axis. After the MCNP is operated, an output file of the MCNP is opened, corresponding output Keff results are found, and the corresponding results are tidied and counted. Different points of the heat pipe in the MCNP program model are shown in fig. 7 (a), and output results after the MCNP files of the different points are operated are shown in fig. 7 (b). The single heat pipe is arranged in seven different placement points of the reactor core, and the point (6) enables the reactor core to have higher Keff and deeper shutdown depth, so that the heat pipe of the point (6) has stronger heat exchange effect in the reactor core.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples merely represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the utility model. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application is to be determined by the claims appended hereto.
Claims (8)
1. The sodium heat pipe cooling reactor core is characterized in that the structure of the reactor core sequentially comprises the following components from inside to outside:
the reactor comprises a reactor core active area, a radial reflecting layer, a control drum area and a shielding layer;
the core active region includes: fuel rods and sodium heat pipes; the fuel rods and the heat pipes are arranged in a triangle and are wrapped by the regular hexagonal prism matrix;
the radial reflecting layer radially surrounds the regular hexagonal prism substrate;
the control drum area comprises 6 control drums; adjacent control drums are radially angled at 60 degrees and are uniformly distributed within the radial reflective layer.
2. The core of claim 1, wherein the sodium heat pipe is comprised of a shell, a working fluid, and a tube core;
the tube core is a silk-screen tube core;
the material of the tube shell is molybdenum-rhenium alloy.
3. The core of claim 2, wherein the die is an 800 mesh stainless steel metal mesh.
4. The core of claim 1, wherein the fuel rods comprise cylindrical fuel pellets and tubular cladding;
the material of the cladding is molybdenum-rhenium alloy.
5. The core of claim 1, wherein the reflective layer material is BeO.
6. The core of claim 1, wherein the shielding layer is a molybdenum-rhenium alloy.
7. The core of claim 2, 4 or 6, wherein the molybdenum-rhenium alloy is a Mo-14% re alloy.
8. The core of claim 1, wherein the core active region comprises: 90 fuel rods and 37 sodium heat pipes.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202321858496.7U CN220672227U (en) | 2023-07-14 | 2023-07-14 | Sodium heat pipe cooling reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202321858496.7U CN220672227U (en) | 2023-07-14 | 2023-07-14 | Sodium heat pipe cooling reactor core |
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| Publication Number | Publication Date |
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| CN220672227U true CN220672227U (en) | 2024-03-26 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202321858496.7U Active CN220672227U (en) | 2023-07-14 | 2023-07-14 | Sodium heat pipe cooling reactor core |
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2023
- 2023-07-14 CN CN202321858496.7U patent/CN220672227U/en active Active
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