CN205487369U - A spacing guide post for reactor core instrument - Google Patents
A spacing guide post for reactor core instrument Download PDFInfo
- Publication number
- CN205487369U CN205487369U CN201620251182.4U CN201620251182U CN205487369U CN 205487369 U CN205487369 U CN 205487369U CN 201620251182 U CN201620251182 U CN 201620251182U CN 205487369 U CN205487369 U CN 205487369U
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- support
- bearing
- reactor core
- support column
- plate
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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 utility model discloses a spacing guide post for reactor core instrument, include the guide post body of installing simultaneously on bearing plate and reactor core upper plate, the guide post body is mainly by the support post, prop up pipe support, supporting ring and bearing constitute, bearing plate and fixed with the bearing plate is passed on the top of support post, pipe support sets up in the support post and bearing plate and reactor core upper plate are passed respectively to both ends, prop up pipe support's bottom and pass the bearing, the supporting ring sets up between a support post and a pipe support, the supporting ring sets up simultaneously between bearing plate and reactor core upper plate, the bottom of support post sets up in the bearing. Closely cooperating when this guide post utilizes the poor clearance of eliminating between the two of the thermal energy of support post and petaloid bearing to pile the operation with the realization response, a pipe support passes through screw -thread fit with the support post, insert and wear out the support post in, get into fuel assembly upper tube base in, in the pressure vessel tube socket disect insertion pipe support to this realizes whole direction and protection to the reactor core instrument.
Description
Technical field
This utility model belongs to the dependency structure that in-pile instrument carries out guide and limit of nuclear reactor structure, is specifically related to a kind of spacing lead for in-pile instrument.
Background technology
Nuclear reactor, is also called atomic reactor or reactor, is controlled self-sustaining chain nuclear fission to be maintained to react, to realize the device of nuclear energy uses.The uncontrolled chain reaction occurred relative to nuclear weapon instant of detonation, among reactor, the speed that core becomes can be precisely controlled, its energy outwards can discharge with slower speed, utilize for people, nuclear reactor passes through reasonable Arrangement nuclear fuel so that without self-sustaining chain nuclear fission process occurring wherein under conditions of adding neutron source.This term of reactor should cover fission-type reactor, fusion reactor, fission fusion hybrid reactor, but the most only refers to fission-type reactor.The in-pile instrument of nuclear reactor typically inserts in heap from pressure vessel top, and after insertion reaction heap, in-pile instrument needs through in-pile component, arrive the measurement position in fuel assembly, and in-pile instrument belongs to slim-lined construction, it is easy to bent by the impact generation of reactor core lateral current, cause using.
Utility model content
Technical problem to be solved in the utility model is that existing in-pile instrument length is long, external diameter is less, it is difficult to after bending insert fuel assembly and be easily subject to lateral current impact, purpose is to provide a kind of spacing lead for in-pile instrument, this spacing lead is used for realizing after in-pile instrument penetrates in reactor, fuel assembly can be inserted smoothly, do not affected by the impact of reactor coolant lateral current, solve existing in-pile instrument length long, external diameter is less, the problem being difficult to after bending insert fuel assembly and be easily subject to lateral current impact.
This utility model is achieved through the following technical solutions:
A kind of spacing lead for in-pile instrument, including the lead body being simultaneously attached on support plate and reactor core upper plate, described lead body is mainly by support column, Zhi Chengguan, support ring and a bearing are constituted, the top of support column through support plate and is fixed with support plate, Zhi Chengguan is arranged in support column and two ends are each passed through support plate and reactor core upper plate, the bottom of Zhi Chengguan is through a bearing, support ring is arranged between support column and Zhi Chengguan, and inwall and the wall contacts of Zhi Chengguan with support column, support ring is simultaneously located between support plate and reactor core upper plate, the bottom of support column is arranged in a bearing, and a bearing is fixed on reactor core upper plate.Owing to existing in-pile instrument length is long, external diameter is less, it is easily bent, after it bends, is difficult to insert fuel assembly, and is easily subject to lateral current impact, and the technical program is guided by the lead of design, achieve the omnidistance guiding to in-pile instrument, and closely cooperating between parts, it is to avoid flow through the coolant side knock to support column of reactor core upper plate, ensure that the structural stability of in-pile instrument, it is simple to its work.
The fastening bolt propped up between bearing and reactor core upper plate is preferably four, fastening bolt between support plate and support column is preferably four, the support column of spacing lead is arranged on in-pile component support plate by four fastening bolts, and petal bearing is arranged on in-pile component reactor core upper plate by four fastening bolts；Support column passes in-pile component support plate, it is inserted directly in petal bearing, it is matched in clearance with petal bearing, support column material is rustless steel, petal bearing materials is nickel-base alloy, owing to the thermal coefficient of expansion of support column is more than a bearing, when reactor operation, the thermal expansion difference of support column and petal bearing counteracts the gap between support column and petal bearing, achieve closely cooperating between support column and petal bearing, avoid the coolant flowing through reactor core upper plate to the side knock of support column, support column is caused to rock abrasion in petal bearing, and support column can keep in repair after dismantling or change.
Zhi Chengguan is by carry out upper end spacing with the threaded engagement of support column, Zhi Chengguan inserts and passes in support column, Zhi Chengguan is designed as variable-diameter structure, lower end and support column are closely cooperating of small gap, a support ring it is welded with in the middle part of Zhi Chengguan, support ring and support column are closely cooperating of small gap, for carrying out spacing to Zhi Chengguan.
The top of spacing lead body does not exceed sealing for pressure vessels face, reduces the height of in-pile component, in order to carry out reloading maintenance operation, and pressure vessel base is inserted directly in the Zhi Chengguan of spacing lead body, it is achieved that the omnidistance guiding to in-pile instrument.
This utility model is compared with prior art; have such advantages as and beneficial effect: closely cooperating when this lead utilizes the thermal expansion difference of support column and petal bearing to eliminate gap between the two to realize reactor operation; Zhi Chengguan and support column pass through threaded engagement; insert and pass in support column; in entrance upper pipe seat of fuel component; pressure vessel base is inserted directly in Zhi Chengguan, realizes guiding the omnidistance of in-pile instrument and protection with this.
Accompanying drawing explanation
Accompanying drawing described herein is used for providing being further appreciated by this utility model embodiment, constitutes the part of the application, is not intended that the restriction to this utility model embodiment.In the accompanying drawings:
Fig. 1 is this utility model scheme of installation in pressure vessel；
Fig. 2 is this utility model structural representation；
Fig. 3 is zoomed-in view at the A of Fig. 2；
Fig. 4 is zoomed-in view at the B of Fig. 2；
Fig. 5 is zoomed-in view at the C of Fig. 2；
Fig. 6 is the top view after petal bearing and support column assembling.
The parts title of labelling and correspondence in accompanying drawing:
1-reactor pressure vessel, 2-pressure vessel base, 3-in-pile component, 4-support plate, 5-reactor core upper plate, 6-lead body, 7-support column, 8-props up and is in the charge of, 9-fastening bolt, 10-support ring, 11-props up bearing, 12-sealing for pressure vessels face, 13-in-pile instrument, 14-upper pipe seat of fuel component, 15-coolant.
Detailed description of the invention
For making the purpose of this utility model, technical scheme and advantage clearer, below in conjunction with embodiment and accompanying drawing, the utility model is described in further detail, exemplary embodiment of the present utility model and explanation thereof are only used for explaining this utility model, are not intended as restriction of the present utility model.
Embodiment:
As shown in Figure 1, the in-pile instrument 13 pressure vessel base 2 from reactor pressure vessel 1 top inserts, the spacing lead body 6 that the present invention relates to is arranged between the support plate 4 of in-pile component 3 and in-pile component reactor core upper plate 5, in wherein pressure vessel base 2 inserts spacing lead body 6, the top specific pressure container sealing surface 12 of spacing lead body 6 is low.
As shown in Figures 2 to 6, spacing lead body 6 is main by support column 7, Zhi Chengguan 8, support ring 10 and a bearing 11 are constituted, the top of support column 7 is fixed through support plate 4 and with support plate 4, Zhi Chengguan 8 is arranged in support column 7 and two ends are each passed through support plate 4 and reactor core upper plate 5, the bottom of Zhi Chengguan 8 is through a bearing 11, support ring 10 is arranged between support column 7 and Zhi Chengguan 8, and inwall and the wall contacts of Zhi Chengguan 8 with support column 7, support ring 10 is simultaneously located between support plate 4 and reactor core upper plate 5, the bottom of support column 7 is arranged in a bearing 11, and a bearing 11 is fixed on reactor core upper plate 5.
Support column 7 is arranged on support plate 4 by four fastening bolts 9, and Zhi Chengguan 8 is inserted in support column 7 by threaded engagement.Being welded with support ring 10 on Zhi Chengguan 8, support ring 10 and support column 7 are close matched in clearance, the most spacing for carrying out Zhi Chengguan 8.Petal bearing 11 is arranged on reactor core upper plate 5 by four fastening bolts 9, and be matched in clearance with support column 7, this gap is eliminated with the thermal expansion difference that material is stainless support column 7 by petal the bearing 11 that material is nickel-base alloy when reactor operation, Zhi Chengguan 8 is variable-diameter structure, insert and pass support column 7, stretch in reactor core upper plate 5, for directly in-pile instrument 13 being introduced in upper pipe seat of fuel component 14, it is achieved that the omnidistance guiding to in-pile instrument.The mid portion of petal bearing 11 is cut into pintongs, and cut part is in order to by coolant 15, and support column 7 inserts and spacing in petal bearing 11.
By the present embodiment, after in-pile instrument penetrates in reactor, fuel assembly can be inserted smoothly, do not affected by the impact of reactor coolant lateral current.
Above-described detailed description of the invention; the purpose of this utility model, technical scheme and beneficial effect are further described; it is it should be understood that; the foregoing is only detailed description of the invention of the present utility model; it is not used to limit protection domain of the present utility model; all within spirit of the present utility model and principle, any modification, equivalent substitution and improvement etc. done, within should be included in protection domain of the present utility model.
Claims (4)
- null1. the spacing lead for in-pile instrument，It is characterized in that，Including the lead body (6) being simultaneously attached on support plate (4) and reactor core upper plate (5)，Described lead body (6) is main by support column (7)、Zhi Chengguan (8)、Support ring (10) and a bearing (11) are constituted，The top of support column (7) is fixed through support plate (4) and with support plate (4)，Zhi Chengguan (8) is arranged in support column (7) and two ends are each passed through support plate (4) and reactor core upper plate (5)，The bottom of Zhi Chengguan (8) is through a bearing (11)，Support ring (10) is arranged between support column (7) and Zhi Chengguan (8)，And inwall and the wall contacts of Zhi Chengguan (8) with support column (7)，Support ring (10) is simultaneously located between support plate (4) and reactor core upper plate (5)，The bottom of support column (7) is arranged in a bearing (11)，And a bearing (11) is fixed on reactor core upper plate (5).
- A kind of spacing lead for in-pile instrument the most according to claim 1, it is characterized in that, it is provided with fastening bolt (9) between described bearing (11) and reactor core upper plate (5), between support plate (4) and support column (7), and fastening bolt (9) is fixed with corresponding a bearing (11), reactor core upper plate (5), support plate (4) or support column (7) respectively.
- A kind of spacing lead for in-pile instrument the most according to claim 2, it is characterised in that the fastening bolt (9) between described bearing (11) and reactor core upper plate (5) is four；Fastening bolt (9) between described support plate (4) and support column (7) is four.
- A kind of spacing lead for in-pile instrument the most according to claim 1, it is characterised in that described support column (7) is inserted in a bearing (11) and forms matched in clearance.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620251182.4U CN205487369U (en) | 2016-03-30 | 2016-03-30 | A spacing guide post for reactor core instrument |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620251182.4U CN205487369U (en) | 2016-03-30 | 2016-03-30 | A spacing guide post for reactor core instrument |
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| Publication Number | Publication Date |
|---|---|
| CN205487369U true CN205487369U (en) | 2016-08-17 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201620251182.4U Active CN205487369U (en) | 2016-03-30 | 2016-03-30 | A spacing guide post for reactor core instrument |
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| CN (1) | CN205487369U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106328230A (en) * | 2016-10-09 | 2017-01-11 | 中国核动力研究设计院 | Guide post for reactor core instrument capable of compensating thermal expansion difference in reactor |
| CN106504801A (en) * | 2016-10-31 | 2017-03-15 | 中国核动力研究设计院 | A kind of can remote disassembling in-pile instrument two stage sealing device |
| WO2024011781A1 (en) * | 2022-07-14 | 2024-01-18 | 中广核工程有限公司 | Reactor core measurement instrument guide assembly |
-
2016
- 2016-03-30 CN CN201620251182.4U patent/CN205487369U/en active Active
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106328230A (en) * | 2016-10-09 | 2017-01-11 | 中国核动力研究设计院 | Guide post for reactor core instrument capable of compensating thermal expansion difference in reactor |
| CN106328230B (en) * | 2016-10-09 | 2018-01-30 | 中国核动力研究设计院 | A kind of in-pile instrument lead that can compensate for reactor thermal expansion difference |
| CN106504801A (en) * | 2016-10-31 | 2017-03-15 | 中国核动力研究设计院 | A kind of can remote disassembling in-pile instrument two stage sealing device |
| CN106504801B (en) * | 2016-10-31 | 2017-12-15 | 中国核动力研究设计院 | It is a kind of can remote disassembling in-pile instrument two stage sealing device |
| WO2024011781A1 (en) * | 2022-07-14 | 2024-01-18 | 中广核工程有限公司 | Reactor core measurement instrument guide assembly |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |