High-temperature reactor core supporting structure cylinder body segmented structure bearing test device and test method

Abstract

The invention relates to the technical field of reactor engineering, in particular to a high-temperature reactor core supporting structure cylinder body segmented structure bearing test device and test method. The device comprises a first simulation shell ring and a second simulation shell ring which are arc-shaped; the upper surface of the upper end plate is connected with a first lifting lug, and the lower surface is connected with a first simulation shell ring; the lower surface of the lower end plate is connected with a second lifting lug, and the upper surface is connected with a second simulation shell ring; the inner clamping plate and the outer clamping plate clamp the joint of the first simulation shell ring and the second simulation shell ring from the two sides and are fixed through the bolt fastener. A plurality of groups of bolt fasteners are provided; the force sensors are arranged on the wall face of the second simulation shell ring and located beside the outmost side and the innermost side of the bolt fasteners respectively. The device is compact in structure and easy to process and manufacture, and the feasibility of module design is verified.

Description

Technical Field

[0001] The invention relates to the field of reactor engineering technology, and in particular to a load-bearing test device and a test method for a barrel segment structure of a high-temperature reactor core support structure. Background Art

[0002] The metal core support structure of the high temperature gas-cooled reactor weighs about 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 metal core support structure adopts a welded structure between the cylinder sections. Due to the existence of many interfaces and the core support work, strict requirements are imposed on the welding deformation of the cylinder sections, making the manufacturing difficult.

[0003] The core support structure is designed with improvements and optimizations, one of the main aspects of which is to implement a segmented modular design for the core. Summary of the invention

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

[0005] The present invention provides a high temperature reactor core support structure barrel segment structure load-bearing test device, comprising:

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

[0007] The first simulated cylinder segment and the second simulated cylinder segment are arc-shaped;

[0008] The upper surface of the upper end plate is connected to a first lifting lug, and the lower surface is connected to a 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 clamping plate and the outer clamping plate clamp the connection between the first simulated cylinder section and the second simulated cylinder section from both sides, and fix them by bolt fasteners;

[0011] There are multiple groups of bolt fasteners;

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

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

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

[0015] Preferably, two second lifting ears are provided, 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, there are 10 to 30 groups of bolt fasteners.

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

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

[0020] The present invention provides a load-bearing test method for a high-temperature reactor core support structure barrel segment structure, comprising the following steps:

[0021] Step 1: The lifting device is connected to the first lifting eye, and the counterweight is connected to the second lifting eye;

[0022] Step 2: Start the static load test. The lifting equipment lifts the test device and the counterweight. The height of the counterweight from the ground should be no less than 0.1m.

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

[0024] Preferably, the counterweight remains off the ground for at least 1 hour.

[0025] Compared with the prior art, the high-temperature reactor core support structure barrel segment structure load-bearing test device and test method of the present invention have a compact structure and are easy to process and manufacture; they can simulate core support structure products and facilitate the design improvement and optimization of the core structure. BRIEF DESCRIPTION OF THE DRAWINGS

[0026] Figure 1 A schematic diagram showing a load-bearing test device for a high-temperature reactor core support structure barrel segment structure;

[0027] Figure 2 A partial cross-sectional view showing the bolt connection structure of the barrel section;

[0028] In the figure:

[0029] 10 is the first lifting ear; 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 ear; 70 is the lower end plate; 80 is the bolt fastener; 90 is the force sensor. DETAILED DESCRIPTION

[0030] In order to further understand the present invention, the embodiments of the present invention are described below in conjunction with examples, but it should be understood that these descriptions are only for further illustrating the features and advantages of the present invention, rather than limiting the present invention.

[0031] The embodiment of the present invention discloses a high temperature reactor core support structure barrel segment structure load bearing test device, such as Figure 1 As shown, including:

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

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

[0034] Considering the convenience of the test, the first simulated cylinder segment 30 and the second simulated cylinder segment 50 are both one-fifth of a circle arc. The ratio of the diameter to the core support structure product is 1:1, and the height is shortened, which has no effect on the test results.

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

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

[0037] The arc centerline of the first simulated cylinder 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] There are two second lifting ears, which are respectively located on both sides of the lower surface of the lower end plate 70 and are symmetrically distributed.

[0040] The arc centerline of the second simulated cylinder section 50 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 cylinder section 30 and the second simulated cylinder section 50 from both sides, and fix them by bolt fasteners 80;

[0042] The inner clamping plate 40, the outer clamping plate 41 and the bolt fasteners 80 are provided in multiple groups 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 group of connecting members, and the connecting members are evenly or unevenly arranged along the arc surface of the first simulated cylinder segment 30 and the second simulated cylinder segment 50; when unevenly arranged, it is preferred that the connecting members are symmetrically arranged with the arc center line of the cylinder segment as the symmetry axis;

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

[0045] Preferably, through holes are provided at the lower part of the first simulated cylinder section 30 and the upper part of the second simulated cylinder section 50, and through holes are also provided on the inner deck 40 and the outer deck 41. Connecting sleeves are provided in the through holes, and the bolt fasteners 80 pass through the connecting sleeves for easy fixation.

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

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

[0048] The present invention also discloses a method for carrying a load on a barrel section structure of a core support structure of a high temperature reactor using the barrel section structure load bearing test device of the core support structure described in the technical solution, comprising the following steps:

[0049] Step 1: The lifting device is connected to the first lifting eye, and the counterweight is connected to the second lifting eye;

[0050] Step 2: Start the static load test. The hoisting equipment lifts the test device and the counterweight. The height of the counterweight from the ground should be no less than 0.1m. The counterweight should remain off the ground for at least 1 hour.

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

[0052] During the test, no parts damage, failure or excessive deformation were found in the test device during the entire static load process.

[0053] If the test device deforms ≥3mm during the entire static load process, it is considered as excessive deformation.

[0054] The test device of the present invention can simulate the core support structure itself, and through the simulation of the test device, the feasibility of the barrel segment structure is determined, which is convenient for the design improvement and optimization of the core structure.

[0055] The above embodiments are only used to help understand the method and core idea of ​​the present invention. It should be noted that, for those skilled in the art, several improvements and modifications can be made to the present invention without departing from the principles of the present invention, and these improvements and modifications also fall within the scope of protection of the claims of the present invention.

[0056] The above description of the disclosed embodiments enables one skilled in the art to implement or use the present invention. Various modifications to these embodiments will be apparent to one 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 present invention. Therefore, the present invention will not be limited to the embodiments shown herein, but rather to the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. High temperature reactor core support structure barrel segment structure load-bearing test device, characterized in that: include: A first simulated cylinder section, a second simulated cylinder section, an upper end plate, a lower end plate, a first lifting lug, a second lifting lug, a force sensor, an inner clamping plate and an outer clamping plate; The first simulated cylinder segment and the second simulated cylinder segment are arc-shaped; The upper surface of the upper end plate is connected to a first lifting lug, and the lower surface is connected to a first simulated cylinder section; 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; The inner clamping plate and the outer clamping plate clamp the connection between the first simulated cylinder section and the second simulated cylinder section from both sides, and fix them by bolt fasteners; There are multiple groups of bolt fasteners; The force sensor is arranged on the wall surface of the second simulated cylinder section, next to each of the outermost and innermost groups of bolt fasteners.

2. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: The first simulated cylinder segment and the second simulated cylinder segment both adopt one-fifth of a circle arc.

3. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: There are two first lifting ears, which are respectively located on both sides of the upper surface of the upper end plate and are symmetrically distributed.

4. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: The second lifting ears are provided in two numbers, which are respectively located on both sides of the lower surface of the lower end plate and are symmetrically distributed.

5. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: The bolt fastener passes through the connecting sleeve.

6. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: There are 10 to 30 groups of bolt fasteners.

7. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: The arc centerline of the first simulated cylinder section is located at the center of the upper end plate.

8. The high temperature reactor core support structure barrel segment structure load bearing test device according to claim 1, characterized in that: The arc centerline of the second simulated cylinder section is located at the center of the lower end plate.

9. High temperature reactor core support structure barrel segment structure load bearing test method, characterized in that: The following steps are involved: Step 1: The lifting device is connected to the first lifting eye, and the counterweight is connected to the second lifting eye; Step 2: Start the static load test. The lifting equipment lifts the test device and the counterweight. The height of the counterweight from the ground should be no less than 0.1m. Step 3: Record the deformation and strain of the barrel at the bolt fasteners, and observe and record the deformation and final damage of the barrel segment structure load-bearing test device of the high-temperature reactor core support structure.

10. The high temperature reactor core support structure barrel segment structure load bearing test method according to claim 9, characterized in that: Keep the weight off the ground for at least 1 hour.

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