CN201111965Y - Pressureized water reactor fuel assembly upper tube socket - Google Patents
Pressureized water reactor fuel assembly upper tube socket Download PDFInfo
- Publication number
- CN201111965Y CN201111965Y CNU2007201815946U CN200720181594U CN201111965Y CN 201111965 Y CN201111965 Y CN 201111965Y CN U2007201815946 U CNU2007201815946 U CN U2007201815946U CN 200720181594 U CN200720181594 U CN 200720181594U CN 201111965 Y CN201111965 Y CN 201111965Y
- Authority
- CN
- China
- Prior art keywords
- fuel assembly
- holddown spring
- depression bar
- spring device
- deckle board
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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Classifications
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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 relates to the field of nuclear fuel components, in particular to an upper tube seat of a pressure water reactor fuel element. A pressure spring device of the utility model is arranged between an upper grid plate and an upper frame plate, only the upper end of a pressure bar extends out from a through hole which is arranged on the upper frame plate; due to the simplification of the part of the spring device above the upper tube seat, the space is saved and the pressure spring device can be evenly distributed at the four corners of the upper tube seat, thus the force which is exerted on the fuel element is uniform and the safe performance can be improved. Meanwhile, the four corners are respectively and symmetrically provided with positioning pin holes, so that the assembly of the pressure water reactor fuel element can be more flexible and convenient.
Description
Technical field
The utility model relates to the nuclear fuel element field, is specifically related to base on a kind of PWR fuel assembly.
Background technology
PWR fuel assembly is the core component in the presurized water reactor, is the place that produces heat, and its design relation is to security, reliability and the economy of presurized water reactor.
Be provided with the holddown spring device on the PWR fuel assembly in the base.Rely on the holddown spring of reactor compacting part in pressing down the holddown spring device, make fuel assembly bear enough axle pressures, to prevent fuel assembly because the upwards hydraulic action of cooling medium and play.In addition, when reactor operation, because fuel assembly is fixed between the reactor core upper and lower plates, and the thermal expansion of fuel assembly and in-pile component is different with the irradiation growth amount, therefore the holddown spring device on the fuel assembly has also played the effect of compensation, make fuel assembly that more growing space be arranged, thereby assembly flexural deformation is suitably controlled.Four groups of laminated springs of the general employing of base on the existing PWR fuel assembly, laminated spring takes up room bigger, can only be fixed on the top, two diagonal angles of base, because it is non-all to layout, the fuel assembly discontinuity, the destruction that may bend, in addition, base is provided with dowel hole at diagonal position on the existing PWR fuel assembly, and installation direction is restricted.
Summary of the invention
The purpose of this utility model is to provide a kind of fuel assembly that makes stressed evenly, base on the higher PWR fuel assembly of security performance.
The utility model is achieved in that base on a kind of PWR fuel assembly, it comprises upper grid plate, be located at the last deckle board of upper grid plate top, between upper grid plate and last deckle board, be provided with the holddown spring device, the holddown spring device comprises depression bar, be with holddown spring in the depression bar outside, above holddown spring, pass depression bar and be provided with pressure cap, pressure cap is in the lower end that abuts against deckle board under the effect of holddown spring, stretch out from the through hole that last deckle board is provided with the upper end of depression bar, and the lower end of depression bar 8 extend in the set through hole of upper grid plate 4.
In the utility model, the holddown spring device is located between upper grid plate and the last deckle board, have only the upper end of depression bar to stretch out from the through hole that last deckle board is provided with, owing to simplified the part of spring assembly above last base, saved the space, so the holddown spring device can evenly distribute at the corner location of last base, thereby make fuel assembly stressed evenly, improved security performance.Simultaneously, at corner location difference symmetric arrangement dowel hole, thereby make the installation of PWR fuel assembly more flexible.
Description of drawings
Fig. 1 is the front elevation of base on a kind of PWR fuel assembly provided by the utility model;
Fig. 2 is the vertical view of base on a kind of PWR fuel assembly provided by the utility model;
Synoptic diagram when Fig. 3 is the work of base on a kind of PWR fuel assembly provided by the utility model;
Among the figure: 1 dowel hole, deckle board on 2,3 holddown spring devices, 4 upper grid plates, 5 pressure caps, 6 pins, 7 holddown springs, 8 depression bars.
Embodiment
As Fig. 1～shown in Figure 2, base on a kind of PWR fuel assembly, it comprises upper grid plate 4, be located at the last deckle board 2 of upper grid plate 4 tops, be provided with holddown spring device 3 between upper grid plate 4 and last deckle board 2, holddown spring device 3 comprises depression bar 8, be with holddown spring 7 in depression bar 8 outsides, depression bar 8 comprises different two sections of tactical diameter, and one section of upper end is thick, and one section of lower end is thin.Above holddown spring 7, pass depression bar 8 pressure cap 5 is installed, pressure cap 5 is fixed on the depression bar by pin, pressure cap 5 is in the lower end that abuts against deckle board 2 under the effect of holddown spring 7, stretch out from the through hole that last deckle board 2 is provided with the upper end of depression bar 8, and the lower end of depression bar 8 extend in the set through hole of upper grid plate 4.Corner location at last deckle board 2 is respectively equipped with dowel hole 1.
The installation process of holddown spring device 3 of the present utility model is as follows:
Pressure cap 5 and holddown spring 7 are put between upper grid plate 4 and the last deckle board 2, and this moment, holddown spring 7 should be compressed a segment distance, produced certain pretightning force; Put into depression bar 8, arrive certain position, depression bar 8 and pressure cap 5 are joined pin hole of brill; Pin 6 is put into the pin hole that is bored, and spot welding is locked.
Principle of work of the present utility model is: after these parts of holddown spring device 3 install by above package, because holddown spring 7 designs have certain pretightning force, therefore do not have external force to make time spent holddown spring device 3 and will be fixed on the position of requirement.When depression bar 8 upper ends were subjected to downward power greater than the holddown spring pretightning force, as shown in Figure 3, depression bar 8 can move down along the through hole of last deckle board 2 and upper grid plate 4; After removing this power, the holddown spring device resets under the effect of spring force.
In when operation in the heap, the reactor compacting part is pressed in directly on the fuel assembly that uniform many covers compress on the spring assembly 3 in the base, promptly is pressed in the top of each depression bar 8.Many covers compress spring assembly 3 pressure of compacting part are delivered on the stressed member of fuel assembly uniformly.The pressure that holddown spring device 3 is subjected in working order should both can prevent fuel assembly because the upwards hydraulic action of cooling medium and play, can effectively control the fuel assembly flexural deformation that causes because of thermal expansion and irradiation growth again, make fuel assembly can keep normal duty.
The corner location of going up deckle board 2 of the present utility model is respectively equipped with dowel hole 1, and fuel assembly can be with the arbitrarily angled reactor core of packing into, makes the fuel assembly can be with the different angles reactor core of packing in each circulation, thereby makes in the assembly burnup more even.
Claims (2)
1. base on the PWR fuel assembly, it comprises upper grid plate (4), be located at the last deckle board (2) of upper grid plate (4) top, it is characterized in that: between described upper grid plate (4) and last deckle board (2), be provided with holddown spring device (3), holddown spring device (3) comprises depression bar (8), be with holddown spring (7) in depression bar (8) outside, top in holddown spring (7), pass depression bar (8) and be provided with pressure cap (5), pressure cap (5) abuts against the lower end of deckle board (2) under the effect of holddown spring (7), stretch out from the through hole that last deckle board (2) is provided with the upper end of depression bar (8), and the lower end of depression bar (8) extend in the through hole of upper grid plate (4).
2. base on a kind of PWR fuel assembly as claimed in claim 1 is characterized in that: the corner location of deckle board (2) is respectively equipped with dowel hole (1) on described.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201815946U CN201111965Y (en) | 2007-10-19 | 2007-10-19 | Pressureized water reactor fuel assembly upper tube socket |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2007201815946U CN201111965Y (en) | 2007-10-19 | 2007-10-19 | Pressureized water reactor fuel assembly upper tube socket |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201111965Y true CN201111965Y (en) | 2008-09-10 |
Family
ID=39963708
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNU2007201815946U Expired - Lifetime CN201111965Y (en) | 2007-10-19 | 2007-10-19 | Pressureized water reactor fuel assembly upper tube socket |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201111965Y (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102136303A (en) * | 2010-01-25 | 2011-07-27 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN104575629A (en) * | 2014-12-05 | 2015-04-29 | 上海核工程研究设计院 | Detachable upper pipe seat and guide pipe connecting structure |
| CN105513658A (en) * | 2010-01-25 | 2016-04-20 | 韩电原子力燃料株式会社 | Top nozzle for nuclear fuel assembly having spring insert hole improved in fastening stability and method of manufacturing the same |
| CN106531230A (en) * | 2016-11-18 | 2017-03-22 | 中国核动力研究设计院 | High stability fuel assembly compacting system with variable rigidity and low radiation slack |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN110993127A (en) * | 2019-11-29 | 2020-04-10 | 广东核电合营有限公司 | Nuclear fuel assembly and variable-rigidity pressing device |
-
2007
- 2007-10-19 CN CNU2007201815946U patent/CN201111965Y/en not_active Expired - Lifetime
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102136303A (en) * | 2010-01-25 | 2011-07-27 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN102136303B (en) * | 2010-01-25 | 2014-10-01 | 韩电原子力燃料株式会社 | Hold-down spring unit for top nozzle of nuclear fuel assembly having improved hold-down performance and top nozzle for nuclear fuel assembly having the same |
| CN105513658A (en) * | 2010-01-25 | 2016-04-20 | 韩电原子力燃料株式会社 | Top nozzle for nuclear fuel assembly having spring insert hole improved in fastening stability and method of manufacturing the same |
| CN105513658B (en) * | 2010-01-25 | 2019-07-19 | 韩电原子力燃料株式会社 | The nuclear fuel assembly pipe top nozzle and its manufacturing method of spring jack with stability maintenance improvement |
| CN104575629A (en) * | 2014-12-05 | 2015-04-29 | 上海核工程研究设计院 | Detachable upper pipe seat and guide pipe connecting structure |
| CN106531230A (en) * | 2016-11-18 | 2017-03-22 | 中国核动力研究设计院 | High stability fuel assembly compacting system with variable rigidity and low radiation slack |
| CN106531230B (en) * | 2016-11-18 | 2018-09-11 | 中国核动力研究设计院 | A kind of high stability fuel assembly pressing system of the low Irradiation slack of variation rigidity |
| CN106803432A (en) * | 2017-02-28 | 2017-06-06 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN106803432B (en) * | 2017-02-28 | 2018-05-25 | 中国核动力研究设计院 | A kind of ex-reactor experiment structure of fuel assembly |
| CN110993127A (en) * | 2019-11-29 | 2020-04-10 | 广东核电合营有限公司 | Nuclear fuel assembly and variable-rigidity pressing device |
| CN110993127B (en) * | 2019-11-29 | 2021-08-27 | 广东核电合营有限公司 | Nuclear fuel assembly and variable-rigidity pressing device |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20080910 |