CN114550955B - Nuclear power reactor core thermal simulation device - Google Patents
Nuclear power reactor core thermal simulation device Download PDFInfo
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- CN114550955B CN114550955B CN202210142331.3A CN202210142331A CN114550955B CN 114550955 B CN114550955 B CN 114550955B CN 202210142331 A CN202210142331 A CN 202210142331A CN 114550955 B CN114550955 B CN 114550955B
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- 238000004088 simulation Methods 0.000 title claims abstract description 45
- 239000000446 fuel Substances 0.000 claims abstract description 93
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 14
- 239000000945 filler Substances 0.000 claims description 7
- 229910052759 nickel Inorganic materials 0.000 claims description 7
- 239000004020 conductor Substances 0.000 claims description 3
- 238000012856 packing Methods 0.000 claims description 3
- 238000012360 testing method Methods 0.000 abstract description 16
- 238000013461 design Methods 0.000 abstract description 10
- 238000011160 research Methods 0.000 abstract description 10
- 238000010438 heat treatment Methods 0.000 description 6
- 239000000463 material Substances 0.000 description 5
- 238000000429 assembly Methods 0.000 description 4
- 230000000712 assembly Effects 0.000 description 4
- 239000000956 alloy Substances 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 229910045601 alloy Inorganic materials 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 210000000746 body region Anatomy 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 238000004514 thermodynamic simulation Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The embodiment of the invention provides a nuclear power reactor core thermal simulation device, which comprises: a simulated core barrel, wherein a simulated core is arranged in the simulated core barrel; a simulated core comprising the same number of simulated fuel bodies as the square array of prototype fuel bodies; the filling block comprises a plurality of filling blocks and is used for being arranged in the simulated reactor core cylinder body, and filling gaps between the simulated fuel body and the simulated reactor core cylinder body so as to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core; the interval between each simulated fuel body is consistent with the interval between each prototype fuel body; the simulated fuel bodies are electrically connected with each other to form a circuit so as to enable the simulated reactor core and the prototype reactor core to generate heat in accordance. The embodiment of the invention can be used for core thermal hydraulic test research, and provides more reliable test basis and technical support for core thermal design and safety analysis of square arrangement structures.
Description
Technical Field
The invention relates to a nuclear power reactor core thermal simulation device.
Background
Due to the increasing energy demand, the development of nuclear energy has become one of the important strategic strategies in the sustainable development of national energy. The nuclear power reactor is used as a main device for realizing nuclear energy conversion and is currently used for nuclear power plants and nuclear power ships. After many years of continuous research, a variety of distinctive nuclear power reactor types have now been developed.
The nuclear power reactor core is generally composed of a plurality of fuel bodies, and the square arrangement fuel bodies are typical reactor fuel body structures, such as a bundle type fuel body adopts a square arrangement structure of 14×14, 15×15, 17×17, etc. The safe operation of a nuclear power reactor is always generally focused by various societies, and under the condition that fuel and structural materials are determined, in order to ensure the safe operation of the reactor and ensure that the heat emitted by the reactor core can be safely output under any working condition, a good reactor core flow and heat transfer structure must be designed, and whether a reactor core scheme is feasible or not, how the economy and the safety are coordinated and the reactor needs to be embodied through the study of the thermal engineering water power of the reactor. Therefore, the method has very important significance in actively developing the thermal hydraulic research of the nuclear reactor core related to the safety problem of the nuclear power plant.
The square-arrangement reactor core fuel body is used as a typical reactor core body structure, and the conventional pressurized water reactor fuel body mostly adopts the square-arrangement structure, so that in order to improve the performance of the reactor core and optimize the design of the reactor core, the reactor core thermal hydraulic test research needs to be carried out to obtain the key thermal parameters of the reactor core. In view of the particularity of the reactor fuel body, the out-of-reactor experiment can not be directly developed, and the invention needs to provide a square-arrangement-body nuclear power reactor core thermodynamic simulation device for core thermodynamic test research, so as to provide more reliable test basis and technical support for core thermodynamic design and safety analysis of a square arrangement structure.
While some researches are conducted in the countries such as the united states, france and germany for nuclear power reactor cores, many fuel body researches or core software calculation and analysis are reported in public due to the trade secret, and no reactor core thermal hydraulic test device is reported yet.
Disclosure of Invention
The embodiment of the invention provides a nuclear power reactor core thermal simulation device which is used for researching reactor core thermal hydraulic tests and provides more reliable test basis and technical support for reactor core thermal design and safety analysis of square arrangement structures.
The embodiment of the invention is realized by the following technical scheme:
The embodiment of the invention provides a nuclear power reactor core thermal simulation device, which comprises:
A simulated core barrel, wherein a simulated core is arranged in the simulated core barrel;
A simulated core comprising the same number of simulated fuel bodies as the square array of prototype fuel bodies; and
The filling block comprises a plurality of filling blocks which are arranged in the simulated reactor core cylinder body and are used for filling gaps between the simulated fuel body and the simulated reactor core cylinder body so as to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core;
the interval between each simulated fuel body is consistent with the interval between each prototype fuel body;
The simulated fuel bodies are electrically connected with each other to form a circuit so as to enable the simulated reactor core and the prototype reactor core to generate heat in accordance.
Further, each of the filling blocks has a hollow structure.
Further, the size of the packing is related to the flow area of the simulated core within the simulated core barrel.
Further, the plurality of filling blocks comprise 4 filling blocks with different shapes; the 4 filling blocks with different shapes comprise rectangular filling blocks, right-angle triangular filling blocks, first right-angle trapezoid filling blocks and second right-angle trapezoid filling blocks; the 4 kinds of filling blocks with different shapes are filled in the simulated core cylinder body at the periphery of the simulated core.
Further, the simulated core further comprises:
A plurality of conductive blocks, each conductive block being for connecting a simulated fuel body;
The plurality of conducting plates are used for connecting the conducting blocks and/or conducting bodies which are not connected with the conducting blocks and serve as conductors for connecting the simulated fuel bodies of the unconnected conducting blocks with the conducting blocks, so that the simulated fuel bodies form a circuit through a combination of serial connection and parallel connection; and
And one end of the conductive electrode is used for being connected with the simulated fuel body, and the other end of the conductive electrode is used for being connected with a power supply.
Further, the number of the simulated fuel bodies is 64, and every 16 simulated fuel bodies are mutually connected in series to form a serial body; the 4 series bodies are mutually connected in parallel to form a parallel connection body.
Further, the serial body is a modularized unit, and each modularized unit is provided with two conductive electrodes respectively used for connecting the anode and the cathode of the power supply; the conductive electrode is arranged at the end part of the modularized unit.
Furthermore, the conductive block, the conductive plate and the conductive electrode are all made of nickel materials.
Further, the filling block is also used for filling a gap between the simulated fuel body and the simulated core barrel to avoid side flow of the medium through the simulated fuel body.
Further, the simulated fuel body is of an elongated rectangular structure, and the simulated fuel body is made of nickel-based alloy.
Compared with the prior art, the embodiment of the invention has the following advantages and beneficial effects:
According to the nuclear power reactor core thermal simulation device, the simulation reactor core cylinder body, the simulation reactor core and the filling blocks are adopted, the intervals among the simulation fuel bodies are consistent with the intervals among the prototype fuel bodies, and the simulation reactor core of each simulation fuel body is consistent with the heating of the prototype reactor core, so that the simulation of the prototype reactor core is realized, and further the simulation device provided by the embodiment of the invention can be used for the reactor core thermal hydraulic test research to provide more reliable test basis and technical support for the thermal design and safety analysis of the reactor core with the square arrangement structure.
Drawings
In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the drawings that are needed in the examples will be briefly described below, it being understood that the following drawings only illustrate some examples of the present invention and therefore should not be considered as limiting the scope, and that other related drawings may be obtained from these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic diagram of the layout of a prototype fuel body of a prototype core.
FIG. 2 is a schematic diagram of the layout of a simulated fuel body of a simulated core.
FIG. 3 is a schematic diagram of the connection structure of a simulated fuel body of a simulated core.
FIG. 4 is a schematic top view of a connection structure of a nuclear power core thermal simulation apparatus.
FIG. 5 is a schematic bottom view of a connection structure of a nuclear power core thermal simulation apparatus.
In the drawings, the reference numerals and corresponding part names:
1-prototype fuel body, 2-simulation fuel body, 3-simulation reactor core barrel, 5-conductive block, 6-conductive plate, 7-conductive electrode, 41-rectangular filling block, 42-right-angle triangle filling block, 43-first right-angle trapezoid filling block, 44-second right-angle trapezoid filling block.
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.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: no such specific details are necessary to practice the invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail in order not to obscure the invention.
Throughout the specification, references to "one embodiment," "an embodiment," "one example," or "an example" mean: a particular feature, structure, or characteristic described in connection with the embodiment or example is included within at least one embodiment of the invention. Thus, the appearances of the phrases "in one embodiment," "in an example," or "in an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in any suitable combination and/or sub-combination in one or more embodiments or examples. Moreover, those of ordinary skill in the art will appreciate that the illustrations provided herein are for illustrative purposes and that the illustrations are not necessarily drawn to scale. The term "and/or" as used herein includes any and all combinations of one or more of the associated listed items.
In the description of the present invention, the terms "front", "rear", "left", "right", "upper", "lower", "vertical", "horizontal", "high", "low", "inner", "outer", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, merely to facilitate description of the present invention and simplify description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the scope of the present invention.
Examples
For providing more reliable test basis and technical support for core thermal design and safety analysis of square array structure for core thermal hydraulic test research, referring to fig. 1-5, an embodiment of the invention provides a nuclear power core thermal simulation device, which comprises: a simulated core barrel 3 in which a simulated core is arranged; a simulated core comprising the same number of simulated fuel bodies 2 as the square array of prototype fuel bodies 1; the filling block comprises a plurality of filling blocks and is used for being arranged in the simulated reactor core cylinder body, and filling gaps between the simulated fuel body and the simulated reactor core cylinder body so as to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core; the interval between each simulated fuel body is consistent with the interval between each prototype fuel body; the simulated fuel bodies are electrically connected with each other to form a circuit so as to enable the simulated reactor core and the prototype reactor core to generate heat in accordance.
Alternatively, the pitch between each of the dummy fuel bodies is identical to the pitch between each of the prototype fuel bodies, meaning that the difference between the pitch between each of the dummy fuel bodies and the pitch between each of the prototype fuel bodies is negligible.
Alternatively, the flow area of the simulated core being consistent with the flow area of the prototype core means that the difference between the flow area of the simulated core and the flow area of the prototype core is negligible.
Alternatively, the simulated core and the prototype core heat are identical, meaning that the difference in heat generation conditions of the simulated core and the prototype core is negligible.
Therefore, the simulation device provided by the embodiment of the invention realizes the simulation of the prototype core by simulating the core cylinder, the simulation core and the filling blocks and enabling the interval between each simulation fuel body to be consistent with the interval between each prototype fuel body, so that the simulation core of each simulation fuel body is consistent with the heating of the prototype core, and further the simulation device provided by the embodiment of the invention can be used for the thermal hydraulic test research of the core to provide more reliable test basis and technical support for the thermal design and safety analysis of the square-arrangement-structure core.
Further, the filling block is also used for filling a gap between the simulated fuel body and the simulated core barrel to avoid side flow of the medium through the simulated fuel body.
Further, each of the filling blocks has a hollow structure. Further, the size of the packing is related to the flow area of the simulated core within the simulated core barrel.
Optionally, the size of the filler block is calculated and adjusted according to the core flow area, and the filler block is internally hollowed out to reduce the weight of the core mold.
Further, the plurality of filling blocks comprise 4 filling blocks with different shapes; the 4 filling blocks with different shapes comprise rectangular filling blocks, right-angle triangular filling blocks, first right-angle trapezoid filling blocks and second right-angle trapezoid filling blocks; the 4 kinds of filling blocks with different shapes are filled in the simulated core cylinder body at the periphery of the simulated core.
Specifically, referring to fig. 1, the simulation object is a selected prototype square arrangement component core main body region (the number of components in the region needs to be even), and is square arrangement, and the invention takes 64 prototype fuel bodies as an example, and each group of prototype fuel bodies is independently arranged. In order to facilitate the realization of the simulation of the electrified heating of the simulated reactor core, and to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core, the simulated reactor core is properly adjusted according to the prototype reactor core arrangement, filling blocks are added into the simulated reactor core, the adjusted simulated reactor core arrangement is shown in fig. 2, the number of the simulated fuel bodies and the gaps among the simulated fuel bodies are consistent with those of the prototype reactor core, the filling blocks are added on the periphery of the reactor core to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core, and the side flow of a medium passing through a unit assembly can be avoided. There are 4 kinds of stainless steel material filling blocks in total, namely, a rectangular filling block 41, a right triangle filling block 42, a first right trapezoid filling block 43 and a second right trapezoid filling block 44, according to the shape of the filling region.
Further, the simulated core further comprises:
A plurality of conductive blocks, each conductive block being for connecting a simulated fuel body;
The plurality of conducting plates are used for connecting the conducting blocks and/or conducting bodies which are not connected with the conducting blocks and serve as conductors for connecting the simulated fuel bodies of the unconnected conducting blocks with the conducting blocks, so that the simulated fuel bodies form a circuit through a combination of serial connection and parallel connection; and
And one end of the conductive electrode is used for being connected with the simulated fuel body, and the other end of the conductive electrode is used for being connected with a power supply.
Referring to fig. 3, the nuclear power core thermal simulation apparatus includes a simulation fuel body, a conductive block 5, a conductive plate 6, and a conductive electrode 7. In order to simulate the heating characteristics of the prototype pile-up assembly by the simulated fuel body, the simulated fuel body is required to generate heat by conducting current, so that the simulated fuel body is provided with a conductive block 5 and a conductive electrode 7, the conductive block 5 is used for connecting the simulated fuel body, the conductive electrode 7 is used for connecting a power supply, and the conductive block 5 and the simulated fuel body 2 are subjected to the effects of circuit series connection and re-parallel connection through a conductive plate 6.
The conductive blocks 5, the conductive plates 6 and the conductive electrodes 7 are made of pure nickel (N6), the conductive plates in various shapes are arranged according to different arrangement modes of the unit components, the separated conductive plates are connected with the upper conductive block and the lower conductive block of the unit components into a whole through laser welding, heating current is led in and led out, circuit connection among the unit components is realized, and the reactor core simulator can conduct current and generate heat after being electrified.
Further, the number of the simulated fuel bodies is 64, and every 16 simulated fuel bodies are mutually connected in series to form a serial body; the 4 series bodies are mutually connected in parallel to form a parallel connection body.
Optionally, the resistance value of the simulated fuel body 2 after voltage application should generate heat in accordance with the heat generated by the prototype reactor core fuel assembly, and through selection and design calculation, the simulated fuel body adopts nickel-based alloy materials with relatively stable electrical performance at high temperature, every 16 simulated fuel bodies 2 are firstly connected in series to form a serial body, and then 4 groups of serial bodies are connected in parallel to form a parallel body.
Further, the serial body is a modularized unit, and each modularized unit is provided with two conductive electrodes respectively used for connecting the anode and the cathode of the power supply; the conductive electrode is arranged at the end part of the modularized unit.
In order to reduce the welding and assembling difficulties of the simulated fuel bodies, the simulated reactor core adopts a modularized design, and 16 simulated fuel bodies are firstly connected in series into 1 modularized unit, and the total number of the modularized units is 4. Each modularized unit is provided with 2 conductive electrodes 7 which are respectively connected with the positive electrode and the negative electrode of the power supply, the conductive electrodes 7 are arranged below the assembly so as to be convenient for power supply connection, and finally 4 modularized units are connected in parallel on the same power supply. The electrical connections inside each modular unit mainly follow the following principle:
(1) All the simulated fuel bodies need to be connected, and the connection cannot be staggered and interfered;
(2) Each modularized unit is required to internally complete component connection, and the connection relation among unit modules is not generated;
(3) Each modularized unit electrode is symmetrically arranged, and the reactor core is led out from the lower part of the simulated fuel body.
Furthermore, the conductive block, the conductive plate and the conductive electrode are all made of nickel materials.
Further, the simulated fuel body is of an elongated rectangular structure, and the simulated fuel body is made of nickel-based alloy.
Through design optimization, the upper and lower connecting structures of the reactor cores of the 64 simulated fuel bodies 2 are respectively shown in fig. 4 and 5, and the positions of the 64 simulated fuel bodies are shown by numbers in the drawings. Wherein the electrodes A1-A4 are converged at the center of the simulated reactor core and are connected with the anode of the power supply device, and the electrodes B1-A4 are connected with the cathode of the power supply device.
Therefore, the nuclear power reactor core thermal simulation device provided by the embodiment of the invention can better simulate a square-arrangement fuel assembly multi-component reactor core, and for the square-arrangement fuel assembly reactor core, the simulation of the prototype pile type flow is realized by reasonably arranging the simulation assemblies and adding the filling block assemblies into the simulation reactor core assembly, and the simulation of the heating characteristics of the prototype pile type assemblies by the simulation reactor core assembly degree is realized by the serial connection and the parallel connection of the simulation assemblies.
The device can reflect the thermodynamic and hydraulic characteristics of the reactor core, and can acquire key thermodynamic parameters such as reactor core flow pressure drop, flow field distribution, temperature field distribution, flow distribution and the like by developing the thermodynamic test study of the reactor core, thereby ensuring the successful completion of the thermodynamic test study of the multi-component reactor core.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.
Claims (8)
1. A nuclear power core thermal simulation apparatus, comprising:
A simulated core barrel, wherein a simulated core is arranged in the simulated core barrel;
A simulated core comprising the same number of simulated fuel bodies as the square array of prototype fuel bodies; and
The filling block comprises a plurality of filling blocks which are arranged in the simulated reactor core cylinder body and are used for filling gaps between the simulated fuel body and the simulated reactor core cylinder body so as to enable the flow area of the simulated reactor core to be consistent with that of the prototype reactor core;
the interval between each simulated fuel body is consistent with the interval between each prototype fuel body;
Each simulated fuel body is electrically connected with each other to form a circuit so as to enable the simulated reactor core and the prototype reactor core to generate heat in accordance;
the size of the packing blocks is related to the flow area of the simulated core within the simulated core barrel;
the filling blocks comprise 4 filling blocks with different shapes; the 4 filling blocks with different shapes comprise rectangular filling blocks, right-angle triangular filling blocks, first right-angle trapezoid filling blocks and second right-angle trapezoid filling blocks; the 4 kinds of filling blocks with different shapes are filled in the simulated core cylinder body at the periphery of the simulated core.
2. The nuclear power core thermal simulation apparatus of claim 1, wherein each filler block of the filler blocks has a hollow structure.
3. The nuclear power core thermal simulation apparatus of claim 1, wherein the size of the filler blocks is related to the flow area of the simulated core within the simulated core barrel.
4. The nuclear power core thermal simulation apparatus of claim 1, wherein the number of filler blocks comprises 4 different shaped filler blocks; the 4 filling blocks with different shapes comprise rectangular filling blocks, right-angle triangular filling blocks, first right-angle trapezoid filling blocks and second right-angle trapezoid filling blocks; the 4 kinds of filling blocks with different shapes are filled in the simulated core cylinder body at the periphery of the simulated core.
5. The nuclear power core thermal simulation apparatus of claim 1, wherein the simulated core further comprises:
A plurality of conductive blocks, each conductive block being for connecting a simulated fuel body;
The plurality of conducting plates are used for connecting the conducting blocks and/or conducting bodies which are not connected with the conducting blocks and serve as conductors for connecting the simulated fuel bodies of the unconnected conducting blocks with the conducting blocks, so that the simulated fuel bodies form a circuit through a combination of serial connection and parallel connection; and
And one end of the conductive electrode is used for being connected with the simulated fuel body, and the other end of the conductive electrode is used for being connected with a power supply.
6. The nuclear power core thermal simulation apparatus of claim 5, wherein the number of simulated fuel bodies is 64, each 16 simulated fuel bodies being connected in series with each other to form a serial body; the 4 series bodies are mutually connected in parallel to form a parallel connection body.
7. The nuclear power core thermal simulation device of claim 6, wherein the series body is a modularized unit, and each modularized unit is provided with two conductive electrodes respectively used for connecting the anode and the cathode of a power supply; the conductive electrode is arranged at the end part of the modularized unit.
8. The nuclear power core thermal simulation apparatus of any one of claims 5-7, wherein the conductive block, the conductive plate, and the conductive electrode are all made of nickel.
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| CN107240427A (en) * | 2017-06-26 | 2017-10-10 | 中国核动力研究设计院 | High temperature resistant cluster fuel assembly analogue means based on Diffusion Welding |
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