Test apparatus and test method for load-bearing capacity of high-temperature reactor core support structure and segmented shell structure

Abstract

This invention relates to the field of reactor engineering technology, and more particularly to a test device and method for testing the load-bearing capacity of a segmented structure supporting the core of a high-temperature reactor. The device includes: a first and a second simulated cylinder section that are arc-shaped; a first lifting lug connected to the upper surface of an upper end plate, and the first simulated cylinder section connected to its lower surface; a second lifting lug connected to the lower surface of a lower end plate, and the second simulated cylinder section connected to its upper surface; inner and outer clamping plates clamping the connection between the first and second simulated cylinder sections from both sides, and securing them with bolts; multiple sets of bolts; force sensors arranged on the wall of the second simulated cylinder section, located next to one set of bolts on the outermost and innermost sides. This invention features a compact structure, is easy to manufacture, and verifies the feasibility of a modular design.

Description

Technical Field

[0001] This invention relates to the field of reactor engineering technology, and in particular to a test device and test method for the load-bearing capacity of the segmented structure of the core support structure of a high-temperature reactor. Background Technology

[0002] The metal core support structure for the high-temperature gas-cooled reactor weighs approximately 430 tons, with an outer diameter of 5.44 meters and a height of about 20 meters. In the completed high-temperature gas-cooled reactor demonstration project (HTR-PM), the cylindrical sections of the metal core support structure are welded together. Due to the numerous joints and the fact that it bears the responsibility of supporting the reactor core, the requirements for welding deformation of the cylindrical sections are stringent, making manufacturing quite challenging.

[0003] The design of the core support structure was improved and optimized, one of the main aspects of which was to implement a segmented modular design for the cylinder. Summary of the Invention

[0004] The technical problem to be solved by this invention is to provide a test device and test method for the load-bearing capacity of the segmented structure of the core support structure of a high-temperature reactor, and to design a modular cylindrical structure to verify the feasibility of the modular design.

[0005] This invention provides a test device for the load-bearing capacity of a segmented structure supporting a high-temperature reactor core, comprising:

[0006] First simulated cylinder section, second simulated cylinder section, upper end plate, lower end plate, first lifting lug, second lifting lug, force sensor, inner clamping plate and outer clamping plate;

[0007] The first and second simulated cylindrical sections are arc-shaped;

[0008] The upper surface of the upper end plate is connected to the first lifting lug, and the lower surface is connected to the first simulated cylinder section;

[0009] The lower surface of the lower end plate is connected to a second lifting lug, and the upper surface is connected to a second simulated cylinder section;

[0010] The inner and outer clamping plates clamp the connection between the first and second simulated cylindrical sections from both sides, and are fixed by bolt fasteners.

[0011] The bolt fasteners are in multiple sets;

[0012] The force sensor is arranged on the wall of the second simulated cylinder section, next to a set of bolt fasteners on the outermost and innermost sides.

[0013] Preferably, both the first and second simulated cylinder sections adopt a one-fifth circular arc.

[0014] Preferably, there are two first lifting lugs, which are located on both sides of the upper surface of the upper end plate and are symmetrically distributed.

[0015] Preferably, there are two second lifting lugs, which are located on both sides of the lower surface of the lower end plate and are symmetrically distributed.

[0016] Preferably, the bolt fastener passes through the connecting sleeve.

[0017] Preferably, the bolt fasteners are in sets of 10 to 30.

[0018] Preferably, the center line of the arc of the first simulated cylinder section is located at the center of the upper end plate;

[0019] The center line of the second simulated cylinder section's curvature is located at the center of the lower end plate.

[0020] This invention provides a test method for the load-bearing capacity of a segmented core support structure of a high-temperature reactor, comprising the following steps:

[0021] Step 1: Connect the lifting equipment to the first lifting lug, and connect the counterweight to the second lifting lug;

[0022] Step 2: Begin the static load test. The lifting equipment will lift the test device and counterweight, with the counterweight at a height of not less than 0.1m from the ground.

[0023] Step 3: Record the deformation and strain of the cylinder at the bolt fasteners, and observe and record the deformation and final failure of the high-temperature reactor core support structure cylinder segment structure bearing test device.

[0024] Preferably, the counterweight should be kept off the ground for at least 1 hour.

[0025] Compared with the prior art, the high-temperature reactor core support structure cylinder segment structure bearing test device and test method of the present invention has a compact structure and is easy to process and manufacture; it can simulate the reactor core support structure product, which facilitates the design improvement and optimization of the reactor core structure. Attached Figure Description

[0026] Figure 1 A schematic diagram of the load-bearing test device for the segmented structure of the core support structure of a high-temperature reactor.

[0027] Figure 2 This is a partial sectional view of the bolted connection structure of the cylinder section;

[0028] In the picture:

[0029] 10 is the first lifting lug; 20 is the upper end plate; 30 is the first simulated cylinder section; 40 is the inner clamping plate; 41 is the outer clamping plate; 50 is the second simulated cylinder section; 60 is the second lifting lug; 70 is the lower end plate; 80 is the bolt fastener; 90 is the force sensor. Detailed Implementation

[0030] To further understand the present invention, embodiments of the present invention are described below in conjunction with examples. However, it should be understood that these descriptions are only for further illustrating the features and advantages of the present invention, and not for limiting the present invention.

[0031] An embodiment of the present invention discloses a load-bearing test device for a segmented structure of a high-temperature reactor core support structure, such as... Figure 1 As shown, it includes:

[0032] First simulated cylinder section 30, second simulated cylinder section 50, upper end plate 20, lower end plate 70, first lifting lug 10, second lifting lug 60, force sensor 90, inner clamping plate 40 and outer clamping plate 41;

[0033] The first simulated cylindrical section 30 and the second simulated cylindrical section 50 are arc-shaped;

[0034] For ease of testing, both the first simulated cylinder section 30 and the second simulated cylinder section 50 are designed with a one-fifth circular arc. The diameter is in 1:1 ratio to the core support structure product, and the height is shortened, but this has no impact on the test results.

[0035] The upper surface of the upper end plate 20 is connected to the first lifting lug 10, and the lower surface is connected to the first simulated cylindrical section 30;

[0036] There are two first lifting lugs, which are located on both sides of the upper surface of the upper end plate 20 and are symmetrically distributed.

[0037] The center line of the first simulated cylindrical section 30 is located at the center of the upper end plate 20;

[0038] The lower surface of the lower end plate 70 is connected to the second lifting lug 60, and the upper surface is connected to the second simulated cylinder section 50;

[0039] The second lifting lug is provided in two parts, which are located on both sides of the lower surface of the lower end plate 70 and are symmetrically distributed.

[0040] The center line of the second simulated cylinder section 50 arc is located at the center of the lower end plate 70.

[0041] The inner clamping plate 40 and the outer clamping plate 41 clamp the connection between the first simulated cylindrical section 30 and the second simulated cylindrical section 50 from both sides, and fix them by bolt fasteners 80.

[0042] Multiple sets of inner clamping plate 40, outer clamping plate 41 and bolt fasteners 80 are provided for connecting and fixing the first simulated cylinder section 30 and the second simulated cylinder section 50.

[0043] An inner clamping plate 40, an outer clamping plate 41, and at least four bolt fasteners 80 constitute a set of connectors. The connectors are evenly or unevenly arranged along the arc surfaces of the first simulated cylindrical section 30 and the second simulated cylindrical section 50. When unevenly arranged, it is preferable that the connectors are symmetrically arranged with the arc center line of the cylindrical section as the axis of symmetry.

[0044] The bolt fasteners 80 are provided in multiple groups, preferably 10 to 30 groups; each group has 4 to 6 bolts.

[0045] Preferably, the lower part of the first simulated cylindrical section 30 and the upper part of the second simulated cylindrical section 50 are provided with through holes, and the inner deck 40 and the outer deck 41 are also provided with through holes. A connecting sleeve is provided in the through hole, and the bolt fastener 80 passes through the connecting sleeve for easy fixing.

[0046] The force sensor 90 is arranged on the wall of the second simulated cylinder section 50, next to a set of bolt fasteners 80 on the outermost and innermost sides.

[0047] The force sensor 90 is used to detect the deformation and strain of the cylinder section.

[0048] This invention also discloses a method for conducting load-bearing tests on high-temperature reactor core support structure segmented structures using the core support structure segmented structure load-bearing test device described above, comprising the following steps:

[0049] Step 1: Connect the lifting equipment to the first lifting lug, and connect the counterweight to the second lifting lug;

[0050] Step 2: Begin the static load test. The lifting equipment will lift the test device and counterweight, with the counterweight at least 0.1m off the ground. The counterweight should remain off the ground for at least 1 hour.

[0051] Step 3: Record the deformation and strain of the cylinder at the bolt fasteners, and observe and record the deformation and final failure of the high-temperature reactor core support structure cylinder segment structure bearing test device.

[0052] During the test, no component failure or excessive deformation was observed in the test device during the entire static load process.

[0053] If the test device exhibits a deformation ≥3mm throughout the static load process, it is considered to have excessive deformation.

[0054] The test apparatus of the present invention can simulate the core support structure itself, and through the simulation of the test apparatus, the feasibility of the segmented shell structure is determined, which facilitates the design improvement and optimization of the core structure.

[0055] The above description of the embodiments is only for the purpose of helping to understand the method and core ideas of the present invention. It should be noted that those skilled in the art can make several improvements and modifications to the present invention without departing from the principles of the present invention, and these improvements and modifications also fall within the protection scope of the claims of the present invention.

[0056] The above description of the disclosed embodiments enables those skilled in the art to make or use the invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the general principles defined herein may be implemented in other embodiments without departing from the spirit or scope of the invention. Therefore, the invention is not to be limited to the embodiments shown herein, but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. A device for testing the load bearing capacity of a segmented structure of a high temperature reactor core support structure barrel, characterized in that, The utility model relates to a kind of high temperature reactor core support structure deformation and strain test device, including: First simulation cylinder section, second simulation cylinder section, upper end plate, lower end plate, first lifting lug, second lifting lug, force sensor, inner clamping plate and outer clamping plate; The first simulation cylinder section and the second simulation cylinder section are circular arc shape; The upper surface of the upper end plate is connected with the first lifting lug, and the lower surface is connected with the first simulation cylinder section; The lower surface of the lower end plate is connected with the second lifting lug, and the upper surface is connected with the second simulation cylinder section; The inner clamping plate and the outer clamping plate clamp the connecting place of the first simulation cylinder section and the second simulation cylinder section from both sides, and are fixed by bolt fastener; The bolt fastener has multiple groups; The force sensor is arranged on the wall surface of the second simulation cylinder section, beside each group of bolt fastener at the outermost and the innermost.

2. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The first simulation cylinder section and the second simulation cylinder section are both one-fifth circular arc.

3. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The first lifting lug is provided with two, respectively located on both sides of the upper surface of the upper end plate, and is symmetrically distributed.

4. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The second lifting lug is provided with two, respectively located on both sides of the lower surface of the lower end plate, and is symmetrically distributed.

5. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The bolt fastener is passed through the connecting sleeve.

6. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The bolt fastener has 10-30 groups.

7. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The first simulation cylinder section arc center line is located at the center position of the upper end plate.

8. The high temperature reactor core support barrel segmented structural load test apparatus of claim 1, wherein, The second simulation cylinder section arc center line is located at the center position of the lower end plate.

9. The method for testing the load bearing of the segmented structure of the barrel of the core support structure of the high temperature reactor according to any one of claims 1 to 8, characterized in that, The utility model includes the following steps: Step one: hoisting equipment is connected with the first lifting lug, and counterweight is connected with the second lifting lug; Step two: start static load test, hoisting equipment hoists test device and counterweight, and the height of counterweight from ground is not less than 0.1m; Step three: record the deformation and strain of the cylinder body at bolt fastener, observe and record the deformation and final failure of high temperature reactor core support structure cylinder body segmented structure load test device.

10. The high temperature reactor core support barrel segmented structural load test method according to claim 9, wherein, After the counterweight leaves the ground, keep at least 1 hour.

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