CN115985531A - New fuel assembly and new control rod assembly inspection bench for marine nuclear power platforms - Google Patents
New fuel assembly and new control rod assembly inspection bench for marine nuclear power platforms Download PDFInfo
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- CN115985531A CN115985531A CN202211719223.4A CN202211719223A CN115985531A CN 115985531 A CN115985531 A CN 115985531A CN 202211719223 A CN202211719223 A CN 202211719223A CN 115985531 A CN115985531 A CN 115985531A
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- fuel assembly
- inspection table
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- 238000007689 inspection Methods 0.000 title claims abstract description 130
- 239000000446 fuel Substances 0.000 title claims abstract description 99
- 238000004088 simulation Methods 0.000 claims abstract description 19
- 230000008093 supporting effect Effects 0.000 claims abstract description 9
- 229910000831 Steel Inorganic materials 0.000 claims description 17
- 239000010959 steel Substances 0.000 claims description 17
- 238000013461 design Methods 0.000 claims description 7
- 229910000975 Carbon steel Inorganic materials 0.000 claims description 3
- 239000010962 carbon steel Substances 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 238000000034 method Methods 0.000 abstract description 9
- 238000000429 assembly Methods 0.000 description 9
- 230000000712 assembly Effects 0.000 description 9
- 238000005259 measurement Methods 0.000 description 5
- 238000003780 insertion Methods 0.000 description 4
- 230000037431 insertion Effects 0.000 description 4
- 239000000463 material Substances 0.000 description 3
- 230000007613 environmental effect Effects 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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- 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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a reactor new fuel assembly and a new control rod assembly inspection desk suitable for an ocean nuclear power platform, wherein the inspection desk comprises: the inspection table bracket comprises an upper bracket, a middle bracket and a lower bracket, and each bracket is respectively provided with an upper inspection table surface, a middle inspection table surface and a lower inspection table surface; the reactor core upper grid plate simulation part is welded on the upper inspection table top, and the reactor core lower grid plate simulation part is welded on the lower inspection table top; the control rod guide tube simulator and the support tube respectively penetrate through the upper, middle and lower inspection table surfaces; the control rod simulator is welded with the supporting tube; the new fuel assembly size inspection general gauge fixing bolt is welded and fixed on the lower inspection table top; and the new control rod assembly dimension inspection go gauge fixing bolt is fixed on the lower inspection table top and used for fixing the new control rod assembly dimension inspection go gauge. The inspection table is used for inspecting a new fuel assembly and a new control rod assembly in the process of refueling the marine nuclear power platform and measuring the pulling and inserting friction force of the new control rod assembly.
Description
Technical Field
The invention relates to a novel fuel assembly and a novel control rod assembly inspection device, in particular to a novel fuel assembly and a novel control rod assembly inspection table for an ocean nuclear power platform.
Background
After a reactor of an ocean nuclear power platform operates for a certain period, when nuclear fuel can not maintain certain power, refueling operation must be carried out, and in order to ensure that the size, the appearance, the positioning hook function and the like of a new fuel assembly meet the requirements of the refueling operation and realize the measurement of the plugging friction force of the new control rod assembly, an effective new fuel check facility needs to be designed to ensure that the new fuel assembly meets the design requirements of the reactor when a reactor core is assembled. The ocean nuclear power platform is as carrying on nucleated power device's welded structure steel boat formula floating platform, is in the marine environment of list, pitch, roll, pitch and heave for a long time, and usable space is very big restricted in the boats and ships simultaneously, has had higher requirement to new fuel assembly inspection facility design.
The new fuel assembly and the new control rod assembly inspection facility of the onshore nuclear power station are simple in structure, the inspection task can be completed only by arranging the new fuel assembly and the new control rod assembly gripper hook in the cabin, and the loading work is performed after the inspection is completed. The onshore nuclear power plant considers that the inspection of a new fuel assembly and a new control rod assembly is carried out on land, the operation environment is static, however, the existing inspection facilities cannot meet the inspection work of the new fuel assembly and the new control rod assembly of the marine nuclear power platform under the marine environment condition.
Meanwhile, relevant data show that the existing relevant marine nuclear power devices do not consider changing materials under the marine environment, and operate at a marine nuclear power device guarantee base or a material changing wharf, so that the inspection work of new fuel assemblies and new control rod assemblies in the marine environment is not considered, the inspection mode of the new fuel assemblies and the new control rod assemblies is consistent with that of a land commercial nuclear power station, and fixed inspection facilities are arranged at the wharf to inspect the new fuel assemblies.
From the above, there is no example of inspecting a new fuel assembly and a new control rod assembly under marine environmental conditions at present, and the existing inspection method of the new fuel assembly and the new control rod assembly cannot be realized due to environmental influences and space limitations, so that the risk of safety accidents is too high, and therefore, a facility capable of inspecting the new fuel assembly and the new control rod assembly under marine environments needs to be designed for a marine nuclear power platform.
Disclosure of Invention
Aiming at the current situation that the prior art and the engineering application are lacked, the invention aims to provide a reactor new fuel assembly and a new control rod assembly inspection table suitable for an ocean nuclear power platform, which are used for inspecting the new fuel assembly and the new control rod assembly in the refueling process of the ocean nuclear power platform, so that the new fuel assembly and the new control rod assembly are inspected in the ocean environment, the size, the appearance and the like of the new fuel assembly and the new control rod assembly meet the requirement of core assembly, and the functional integrity of a new fuel assembly positioning hook and the drawing and inserting friction force measurement of the new control rod assembly are ensured.
The technical scheme adopted for realizing the aim of the invention is a new fuel assembly and a new control rod assembly inspection desk for an ocean nuclear power platform, wherein the inspection desk comprises:
the inspection table bracket comprises an upper bracket, a middle bracket and a lower bracket, and each bracket is respectively provided with an upper inspection table surface, a middle inspection table surface and a lower inspection table surface; the middle inspection table top is provided with a through hole;
the reactor core upper grid plate simulation piece is of a circular tubular structure and is welded on the upper inspection table top,
the core lower grid plate simulator is welded on the lower inspection table top
The control rod guide tube simulator is of a circular tube-shaped structure and penetrates through the upper, middle and lower inspection table tops;
the supporting tube penetrates through the upper, middle and lower inspection table boards;
the control rod simulator is welded with the supporting tube;
the new fuel assembly size inspection go gauge fixing bolt is of a cylindrical structure, is welded and fixed on the lower inspection table top and is used for fixing the new fuel assembly size inspection go gauge;
the new control rod assembly dimension inspection general gauge fixing bolt is of a cylindrical structure, is fixed on the lower inspection table top and is used for fixing the new control rod assembly dimension inspection general gauge.
Further, the new fuel assembly and the new control rod assembly inspection bench for the marine nuclear power platform are characterized in that: and a new control rod assembly gripper hook and a new fuel assembly gripper hook are fixed on the inspection table bracket.
In the technical scheme, the size of the new fuel assembly size inspection universal gauge fixing bolt is slightly smaller than that of the fuel assembly, and the size of the new control rod assembly size inspection universal gauge fixing bolt is slightly smaller than the design size of the new control rod.
In the technical scheme, the inspection table bracket is of a frame structure formed by connecting a plurality of transverse channel steel, longitudinal channel steel 14-2 and oblique channel steel.
In the technical scheme, the upper, middle and lower inspection table tops are respectively three L-shaped supports, one surface of each L-shaped support is fixedly connected with the corresponding support, and the other surface of each L-shaped support forms a table top for supporting.
In the above technical solution, the inspection table bracket is made of carbon steel, and the components contacting the fuel and the control rod are made of stainless steel.
The new fuel assembly and the new control rod assembly inspection bench for the marine nuclear power platform can realize that the marine nuclear power platform inspects the new fuel assembly and the new control rod assembly in a swinging and swaying marine environment, so that the size, the appearance and the function of the new fuel assembly and the new control rod assembly meet the design requirements of a reactor during reactor core assembly, and the inspection bench realizes function concentration, reduces the number of equipment and is beneficial to improving the utilization rate of the space inside a cabin of the marine nuclear power platform.
Drawings
FIG. 1 is a schematic diagram of the new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform according to the present invention.
FIG. 2 is an isometric view of the new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform according to the present invention.
FIG. 3 is a top view of the new fuel assembly and new control rod assembly inspection table for an offshore nuclear power platform of the present invention.
In the figure: 1-control rod guide tube simulator; 2, a grid plate simulation piece on the reactor core; 3-control rod simulation; 4-supporting the tube; 5-checking the table top of the table; 6-new control rod assembly gripper hooks; 7-middle table top of the inspection table; 8-new fuel assembly gripper hooks; 9-checking the table top of the table bottom; 10-a core lower grid plate simulation piece; 11-new fuel assembly dimension inspection go gauge I; 12-new fuel assembly size inspection go gauge II; 13-new control rod size inspection go gauge; 14-inspection table brackets (14-1-transverse channel steel, 14-2-longitudinal channel steel, 14-3 oblique channel steel); 15-new fuel assembly through holes; 16 new fuel assembly dimension check go gauge set pin; the new control rod assembly is sized to check the through gauge fixing peg 17.
Detailed Description
The invention is described in further detail below with reference to the figures and the specific embodiments.
As shown in fig. 1-3, the new fuel assembly and new control rod assembly inspection desk for marine nuclear power platform of the present invention comprises a control rod guide tube simulator 1, an upper core grid plate simulator 2, a control rod simulator 3, a support tube 4, a new control rod assembly gripper hook 6, a new fuel assembly gripper hook 8, a lower core grid plate simulator 10, a new fuel assembly dimension inspection go gauge I11, a new fuel assembly dimension inspection go gauge II12, a new control rod dimension inspection go gauge 13, an inspection desk bracket 14, a new fuel assembly dimension inspection go gauge fixing bolt 16, and a new control rod assembly dimension inspection go gauge fixing bolt 17.
The inspection table support 14 is of a frame type as a whole and is used for providing inspection of new fuel assemblies and new control rod assemblies and storage of the grab, so that the space required by the inspection is reduced as much as possible, and the space utilization rate is improved. The inspection table bracket 14 is of a frame structure consisting of a plurality of transverse channel steels 14-1, longitudinal channel steels 14-2 and oblique channel steels 14-3, so that the stability of the bracket is ensured. The inspection station support 14 is made of carbon steel to ensure structural strength and the components in contact with the fuel and control rods are stainless steel to ensure that the materials are compatible with the environment under operating conditions and accident conditions to avoid contamination of the fuel assembly and control rod assembly.
In the embodiment, an upper support, a middle support and a lower support are formed by three transverse channel steel 14-1, an upper table top 5 of an inspection table, a middle table top 7 of the inspection table and a bottom table top 9 of the inspection table are correspondingly arranged on each support, the three table tops are all of an L-shaped structure, one surface of the L-shaped structure is respectively connected with the transverse channel steel 14-1 through bolts, and the other side of the L-shaped structure provides a supporting effect.
The control rod guide tube simulation part 1 is of a circular tube structure, penetrates through an upper table top 5 of an inspection table, and penetrates through three table tops of a middle table top 7 and a bottom table top 9 of the inspection table, and is used for measuring the pulling and inserting friction force of a new control rod, a gripping tool of the new control rod assembly is connected with a crane through a dynamometer during inspection, the crane moves the new control rod assembly to the position right above the control rod guide tube simulation part 1 through the gripping tool of the new control rod assembly, the new control rod assembly is slowly inserted and pulled out, the friction force is measured by the dynamometer when the new control rod assembly is inserted into or pulled out of the control rod guide tube simulation part, and the pulling and inserting friction force measurement of the new control rod assembly is realized. The outer diameter of the control rod guide tube simulator 1 is matched with the maximum outer diameter of a new control rod assembly, the insertion depth of the new control rod assembly is met, the fact that the new control rod assembly can be inserted into or pulled out of the simulator during inspection is guaranteed, the friction force generated when the new control rod assembly is inserted into or pulled out of the control rod guide tube simulator can be measured, and the measurement of the pulling and inserting friction force of the new control rod assembly is achieved.
The reactor core upper grid plate simulation part 2 is of a circular tube structure and is welded on the upper table top 5 of the inspection table, the reactor core lower grid plate simulation part 10 is welded on the bottom table top 9 of the inspection table, and a through hole 15 is formed in the middle table top of the inspection table, so that the insertion of a new fuel assembly is ensured to perform the function inspection of a positioning hook of the new fuel assembly.
The control rod simulator 3 passes through and is stored on the supporting tube 4, the control rod simulator 3 is inserted into a control rod guide tube of a new fuel assembly during inspection, the insertion process is smooth and unimpeded, and then the control rod simulator is drawn out, and the drawing process is smooth and unimpeded. The size of the control rod simulation part is matched with the size of a new control rod, so that the new control rod can be inserted into and pulled out of the guide tube of the new control rod, and the drawing and inserting test of the guide tube of the new control rod is realized.
The new control rod assembly gripper hook 6 and the new fuel assembly gripper hook 8 are fixedly connected with the transverse channel steel 14-1 through bolts, and in order to increase the space utilization rate and avoid interference, the new control rod assembly gripper hook 6 and the new fuel assembly gripper hook 8 can be arranged on different support transverse channel steels 14-1 and are arranged in a longitudinally staggered mode. The gripping apparatus is stored on the hook and fixed by the binding belt so as to adapt to the safe storage requirement under the marine environment condition.
The new fuel assembly size inspection go gauge fixing bolt 16 is fixed on the table top 9 at the bottom of the inspection table through welding, is of a cylindrical structure, is slightly smaller than the size of a new fuel assembly, and is used for fixing a new fuel assembly size inspection go gauge I11 and a new fuel assembly size inspection go gauge II12. The inner diameter of the new fuel assembly size inspection general gauge I11 is matched with the outer diameter of an upper joint of a new fuel assembly, and the inner diameter of the new fuel assembly size inspection general gauge II12 is matched with the outer diameter of an element box, so that the new fuel assembly can smoothly pass through the general gauge, and the size inspection of the new fuel assembly is realized.
The new control rod assembly size inspection go gauge fixing bolt 17 is fixed on the inspection table bottom table top 9 through welding, is of a cylindrical structure, is slightly smaller than the design size of a new control rod, and is used for fixing the new control rod assembly size inspection go gauge 13. The inner diameter of the new control rod assembly dimension inspection go gauge 13 is matched with the maximum outer diameter of a new control rod, so that the new control rod can pass through smoothly, and dimension inspection and appearance inspection of the control rod assembly are realized.
The new fuel assembly and the new control rod assembly inspection bench for the marine nuclear power platform are used in the following processes:
in the process of checking new fuel and a new control rod under the marine environment condition, firstly, a crane is connected with a new fuel assembly gripping apparatus to lift a new fuel assembly above a new fuel assembly size checking universal gauge, an operator holds the new fuel assembly size checking universal gauge I11 and a new fuel assembly size checking universal gauge II12 to penetrate through the new fuel assembly to check the size of the new fuel, after the size is checked, the operator penetrates the new fuel assembly through a reactor core upper grid plate simulation part 2, a new fuel assembly through hole 15 and a reactor core lower grid plate simulation part 10 through the crane to be fixed on a new fuel assembly checking platform, the new fuel assembly gripping apparatus is used for pressing a guide pipe part of the new fuel assembly to check whether a positioning hook boss is successfully and completely retracted into a lower joint; after the acting force of the guide pipe component is removed, whether the boss of the positioning hook smoothly extends out of the lower joint is checked, the lower end of the new fuel assembly is positioned, and the function check of the positioning hook of the new fuel assembly is realized. Insert control rod simulation piece 3 into fuel assembly's control rod stand pipe through the crane, the insertion process guarantees smoothly unimpededly, then takes control rod simulation piece 3 out, and the process of taking out also guarantees smoothly unimpededly, realizes control rod stand pipe part and takes out and insert the experiment. Finally, checking the new control rod assembly, connecting a gripping apparatus of the new control rod assembly through a crane, hoisting the new control rod assembly above a new control rod size checking go-gauge 13, and carrying out size checking on the new control rod assembly by an operator holding the new control rod size checking go-gauge 13 to pass through the new control rod assembly; and then, measuring the pulling and inserting friction force of the new control rod assembly, connecting the new control rod assembly with a crane through a dynamometer, moving the new control rod assembly to the position right above the control rod guide tube simulation piece 1 through a gripping apparatus of the new control rod assembly by the crane, slowly inserting and pulling out the new control rod assembly, and measuring the friction force when the control rod assembly is inserted into or pulled out of the control rod simulation piece by the dynamometer so as to realize the measurement of the pulling and inserting friction force of the control rod. After all the assembly inspections are completed, new fuel assembly grippers and new control rod assembly grippers are respectively bound and fixed on the new fuel assembly gripper hooks 8 and the new control rod assembly hooks 6 for storage.
The design of the inspection table structure and the arrangement of the device ensure safe and reliable inspection of new fuel assemblies and new control rod assemblies under the environment conditions of inclination and swinging.
Claims (6)
1. A new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform, comprising:
the inspection table support (14) comprises an upper support, a middle support and a lower support, and each support is provided with an upper inspection table surface (5,7,9), a middle inspection table surface and a lower inspection table surface (5,7,9); the middle checking table top is provided with a through hole (15);
the reactor core upper grid plate simulation piece (2) is of a circular tubular structure and is welded on the upper inspection table top,
the reactor core lower grid plate simulator (10) is welded on the lower inspection platform surface (9)
The control rod guide tube simulator (1) is of a circular tube-shaped structure and penetrates through the upper, middle and lower inspection table surfaces;
the supporting tube (4) penetrates through the upper, middle and lower inspection table tops;
the control rod simulator (3) is welded with the supporting tube (4);
the new fuel assembly dimension inspection go gauge fixing bolt (16) is of a cylindrical structure, is welded and fixed on the lower inspection table top (9), and is used for fixing the new fuel assembly dimension inspection go gauges (11 and 12);
and the new control rod assembly dimension inspection drift gauge fixing bolt (17) is of a cylindrical structure, is fixed on the lower inspection table top (9) and is used for fixing the new control rod assembly dimension inspection drift gauge (13).
2. The new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform as set forth in claim 1, wherein: and a new control rod assembly gripper hook (6) and a new fuel assembly gripper hook (8) are fixed on the inspection table support.
3. The new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform as set forth in claim 1, wherein: the new fuel assembly dimension check gauge fixing bolt (16) is slightly smaller than the fuel assembly dimension, and the new control rod assembly dimension check gauge fixing bolt (17) is slightly smaller than the new control rod design dimension.
4. The new fuel assembly and new control rod assembly inspection station for a marine nuclear power platform as claimed in claim 1, wherein: the inspection table bracket (14) is a frame structure formed by connecting a plurality of transverse channel steel (14-1), longitudinal channel steel (14-2) and oblique channel steel (14-3).
5. The new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform as set forth in claim 1, wherein: the upper, middle and lower inspection table tops (5,7,9) are respectively three L-shaped supports, one side of each L-shaped support is fixedly connected with the corresponding support, and the other side of each L-shaped support forms a table top for supporting.
6. The new fuel assembly and new control rod assembly inspection station for an offshore nuclear power platform as set forth in any one of claims 1-5, wherein: the inspection table support is made of carbon steel, and the parts in contact with the fuel and the control rods are made of stainless steel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211719223.4A CN115985531A (en) | 2022-12-30 | 2022-12-30 | New fuel assembly and new control rod assembly inspection bench for marine nuclear power platforms |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211719223.4A CN115985531A (en) | 2022-12-30 | 2022-12-30 | New fuel assembly and new control rod assembly inspection bench for marine nuclear power platforms |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN115985531A true CN115985531A (en) | 2023-04-18 |
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ID=85973756
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202211719223.4A Pending CN115985531A (en) | 2022-12-30 | 2022-12-30 | New fuel assembly and new control rod assembly inspection bench for marine nuclear power platforms |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115985531A (en) |
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2022
- 2022-12-30 CN CN202211719223.4A patent/CN115985531A/en active Pending
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