CN1841569B - Method and device for changing nuclear reactor upper component at least a thermoelectric couple column - Google Patents
Method and device for changing nuclear reactor upper component at least a thermoelectric couple column Download PDFInfo
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- CN1841569B CN1841569B CN2006100678424A CN200610067842A CN1841569B CN 1841569 B CN1841569 B CN 1841569B CN 2006100678424 A CN2006100678424 A CN 2006100678424A CN 200610067842 A CN200610067842 A CN 200610067842A CN 1841569 B CN1841569 B CN 1841569B
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- guide pipe
- support plate
- pile
- thermopair
- intermediate structure
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a method for replacing at least one thermal couple plunger inside the upper internal elements (6) of atomic pile, wherein said elements comprise one support plate (80 mounted with guide tube (9) with pile core reaction adjustable rod beam; at least one thermal couple plunger with one serial of thermal couples; and a connector (22) for passing said thermal couple through the support plate (8); and said method comprises: extracting present thermal couple, and taking out replaced thermal couple plunger; positioning and fixing one intermediate structure (41) on the support plate (8); the intermediate structure (41) is mounted with at least one replace thermal couple plunger; said plunger is mounted with upper guide tube (51) for guiding new thermal couple; at the same time, guiding the free end sleeve (51a) of upper guide tube (51) into each selected connector (22), to guide the new thermal couple into upper guide tube (51).
Description
Technical field
The present invention relates to a kind of method and apparatus of changing at least one thermocouple pile in the in-pile component of pressurized-water reactor top.
Background technology
Pressurized-water reactor is included in nuclear reactor in the container and the top in-pile component above the reactor core.Reactor core is that the fuel assembly by the prism-shaped with vertical axis constitutes.The top in-pile component is used to guide the vertical guide pipe of control rod particularly including a cover, and control rod comprises cluster placement parallel to each other and that contain the neutron absorbing material.
In order to control reactor by the reactivity of regulating reactor core, absorb cluster when reactor operation, in the vertical direction moves by a kind of like this mode, and promptly absorbing rod is inserted into some fuel assembly of reactor core to the darker or more shallow degree of depth.
The top in-pile component generally comprises upper plate and lower plate.Upper plate also is referred to as support plate, and lower plate constitutes the upper core plate of nuclear reactor.When the top in-pile component when the reactor in-core is in run location, upper core plate is seated in the upper end of fuel assembly.The vertical guide pipe of guiding control rod is connected to support plate and lower plate.Each guide pipe comprises the first that places between support plate and the lower plate, and the second portion that is fixed on this support plate top.Support column is arranged between support plate and the lower plate, is parallel to guide pipe, makes these plates remain on the fixed position, and provides rigidity for the top in-pile component.
The top in-pile component also comprises instrumentation column, such as columniform thermocouple pile.Being arranged in each thermocouple pile is one group of thermopair, is used to measure the temperature of the cooling medium of a group fuel assembly that leaves previously selected reactor in-core.
The quantity of thermocouple pile generally is two or four.
Each thermocouple pile is not fixed on the support plate of top in-pile component, but is being directed on the vertical sleeve that extends on this support plate, and sleeve runs through thermocouple pile.On the contrary, only utilize the top seal device that each thermocouple pile is fixed on the top cover of reactor vessel, the top seal device is arranged between the top of the ozzle that is fixed on the adapter in the top cover perforate and thermocouple pile.
Therefore, several thermopairs are arranged in the post, and draw from this post, so that each thermopair arrives the joint that is used for by support plate by the peripheral perforate that is formed on this column base plate.For this reason, each joint is provided with main guide pipe, and main guide pipe is arranged to be aligned in the hole that forms on the support plate, and this hole is almost with will to carry out thermometric zone consistent.Therefore thermopair is introduced in the pipe of corresponding joint, and its responsive measuring junction is placed on predetermined measured zone.
When reactor has moved regular hour length, may no longer provide any data this situation by the several thermopairs of alleged occurrence, this means the reliable and representational figure of the actual temperature that no longer has the reactor core cooling medium.
In addition, can not when extracting out, corresponding thermocouple pile must change thermocouple pile fully when some thermopairs.
The purpose of this invention is to provide a kind of method and apparatus that can change at least one thermocouple pile of nuclear reactor at a distance, provide this class to intervene desired all necessary security guarantees simultaneously.
Summary of the invention
Therefore, theme of the present invention is a kind of method of changing at least one thermocouple pile in the nuclear reactor upper in-pile component, and described top in-pile component comprises support plate, and described support plate has:
The reactive cluster guide pipe of regulating of-reactor core;
-described at least one thermocouple pile, it comprise a cover thermopair and by in fixed on a locating sleeve; And
-joint, it is used to make thermopair to pass through described support plate,
It is characterized in that this method comprises the steps:
-the top in-pile component is placed on the underwater worktable;
-extract existing thermopair out;
Described at least one thermocouple pile that-taking-up will be changed;
-by sleeve pipe intermediate structure being positioned on the described support plate, described intermediate structure is equipped with at least one the replacing thermocouple pile that is securely fixed on it, and described replacing thermocouple pile prepackage is useful on the top guide pipe of the new thermopair of guiding; Free end lining with corresponding guide pipe is incorporated in each previously selected joint simultaneously;
-described intermediate structure is fixed on the described support plate;
-new thermopair is incorporated in the guide pipe of corresponding top, up to predetermined working position.
According to another feature of the present invention:
-before being positioned at described intermediate structure on the described support plate, will be used for guiding the middle guide pipe of new thermopair to be incorporated into each previously selected joint,
-middle guide pipe is locked on the described joint,
-before being positioned at described intermediate structure on the described support plate, this intermediate structure is located and be fixed on to the top guide pipe that will be used for new thermopair along predetermined path, make when this intermediate structure is placed on the described support plate downwards, the free end lining of each top guide pipe overlaps with previously selected joint
-when described intermediate structure is placed downwards, described at least one change that thermocouple pile is placed on the pilot sleeve that is associated with the thermocouple pile that will change and
-before changing the thermocouple pile location, the length of pilot sleeve is reduced.
Another theme of the present invention is a kind of device of changing at least one thermocouple pile in the nuclear reactor upper in-pile component, and described top in-pile component comprises support plate, and support plate has:
The reactive guide pipe of regulating cluster of-reactor core;
-comprise one the cover thermopair described at least one thermocouple pile; And
-make thermopair pass through the joint of described support plate,
It is characterized in that, it comprises intermediate structure, described intermediate structure is intended being placed on the support plate downwards by supporting member and at least one the replacing thermocouple pile that is securely fixed on it is installed, described replacing thermocouple pile is equipped with upper guide in advance to pipe, and described upper guide is used for guiding new thermopair until each previously selected joint to pipe.
According to another feature of the present invention:
-intermediate structure is made of the horizontal beam grid that is fixed together, described horizontal beam forms predetermined path, the described top guide pipe that this path allows to be used for new thermopair is connected so that when this intermediate structure is placed on the support plate downwards, the free end lining of each top guide pipe overlaps with previously selected joint
-this device, for each previously selected joint, comprise the middle guide pipe that is used for new thermopair and be connected bell-jar that described connection bell-jar comprises the hole of the free end lining of accepting the respective upper guide pipe on the one hand, comprise the device that is used to be locked in the joint on the other hand
-middle guide pipe is fixed to described connection bell-jar,
-device that the free end lining is locked in the joint is the right-angled bend type, and
-bell-jar comprises fixed system, and this fixed system is for example fixed by clip or the free end lining of the corresponding top of screwed guide pipe works.
Description of drawings
Read provide by example and make with reference to accompanying drawing below instructions after, the present invention is with relatively good understanding, wherein:
Fig. 1 is the cut-open view on the symmetrical vertical plane of a pressurised water nuclear reactor pressure vessel;
Fig. 2 is that the nuclear reactor upper in-pile component is placed on a concise and to the point elevation drawing on the worktable in the reactor pit, is used to change the operation of at least one thermocouple pile;
Fig. 3 is the fragmentary perspective view that the top in-pile component support plate of two thermocouple piles that will change is installed;
Fig. 4 is the fragmentary perspective view of similar Fig. 3, shows the support plate after the thermocouple pile that will change has been pulled out;
Fig. 5 be do not change thermocouple pile according to the fragmentary perspective view of the intermediate structure of changing device more of the present invention;
Fig. 6 is the schematic representation that the intermediate structure of changing thermocouple pile is installed of similar Fig. 5;
Fig. 7 is the concise and to the point axial cut-open view that first embodiment of the joint on the support plate of new thermopair centering device is installed;
Fig. 8 is the concise and to the point axial cut-open view that second embodiment of the joint on the support plate of new thermopair centering device is installed;
Fig. 9 is the concise and to the point skeleton view that is equipped with according to the top in-pile component support plate of the intermediate structure of more changing device of the present invention;
Figure 10 is the elevation drawing of the concise and to the point broken section of intermediate structure, and this intermediate structure is installed on the top in-pile component support plate that has reactor lid.
Embodiment
Fig. 1 has schematically illustrated the container of pressurized-water reactor, represents with label 1.In the usual way, reactor core 2 is arranged in nuclear reactor vessel inside, and comprises the fuel assembly of placing side by side by this way 3, makes that the longitudinal axis of fuel assembly is vertical.Reactor core 2 is arranged in the bottom in-pile component of representing with total mark 4, and the bottom in-pile component specifically comprises core baffle assembly 5.
Nuclear reactor also comprises the top in-pile component of representing with total mark 6, and the top in-pile component is seated on the upper plate of reactor core assembly by upper core plate 7.
As seeing in Fig. 1, top in-pile component 6 comprises a upper plate 8, below will be referred to as support plate 8.This support plate 8 is parallel to upper core plate 7 and extends, and upper core plate 7 constitutes the bottom of top in-pile component 6.This support plate 8 is made by this way to allow the top in-pile component to be connected the inside of container 1.
Top in-pile component 6 comprises the guide pipe of representing with total mark 9.Guide pipe is made of top 9a and bottom 9b.Top 9a has the top that circular cross section and each top 9a are positioned at support plate 8.Bottom 9b have usually the band fillet approximate foursquare xsect and between the support plate 8 and upper core plate 7 of top in-pile component 6.Each part 9a and 9b form the guide pipe 9 of top in-pile component 6, allow to regulate the reactive cluster in the vertical direction of nuclear reactor and regulate.Cluster is connected on suspended axle and the drive unit, and the motion of drive unit in the vertical direction causes that by the not shown mechanism that goes out this mechanism is positioned at the top of the top cover 1a of container 1.
Except the bottom 9b of guide pipe 9, support column 10 is placed between the support plate 8 and upper core plate 7 of top in-pile component 6.Support column 10 makes upper core plate 7 be held in place and keep its spacing with respect to support plate 8.
Fig. 3 schematically illustrates the upper surface of support plate 8 with skeleton view.The upper surface of support plate 8 is equipped with top 9a and two thermocouple piles 20 of guide pipe 9.In the embodiment that this illustrates, two thermocouple piles 20 are parallel to guide pipe 9 and extend above support plate 8.
Usually, what be arranged in each thermocouple pile 20 inside is a cover thermopair 21, is used for measuring the temperature of the cooling medium of the fuel assembly that leaves previously selected one group of nuclear reactor.
As shown in Figure 3, several thermopairs 21 are arranged in the post 20, draw from this post by the unshowned peripheral perforate that forms above the base plate of thermocouple pile 20, so that each thermopair arrives the joint 22 that is used for by support plate 8.In the figure, in order not make this figure overstocked, show the thermopair 21 of limited quantity.These thermopairs 21 generally are placed in the guide pipe of unshowned top.
In order to allow passing through of thermopair 21, each joint 22 is provided with is responsible for 23, is responsible for 23 and is arranged to be aligned in support plate 8 (Fig. 7 and 8) and goes up the hole 24 that forms, and hole 24 is almost with will carry out thermometric zone with corresponding thermopair consistent.
As shown in Figure 4, each thermocouple pile 20 fixed on the abutment sleeve 25 that vertically extends above the support plate 8.
When reactor has moved time of a fixed length, may no longer provide any data this situation by the several thermopairs of alleged occurrence, this means the reliable and representational figure that no longer has reactor core cooling medium actual temperature.
Like this, when the reactor shutdown is overhauled and reloaded, confirm to be necessary to change one or several thermocouple pile and existing thermopair.
For this reason, will comprise that the top in-pile component 6 of lower plate 7, support plate 8, guide pipe 9 and existing thermocouple pile 20 takes out from reactor vessel 1, and be placed on downwards on the worktable set in the reactor pit 30, as shown in Figure 2.For this reason, worktable 30 is equipped with the appropriate device that is used to support top in-pile component 6.
Make reactor pit be filled to its top water level, carry out the operation of every work usually from the passageway of unshowned this water level top, top, pond.
After being placed on top in-pile component 6 on the worktable 30, take out thermocouple pile 20 and thermopair 21.For example, enter the position of joint 22 at thermopair 21 from position that thermocouple pile 20 comes out with at them, cutting thermopair 21 takes out thermocouple pile 20 and and the thermopair that is associated of these posts then.Support plate 8 is in the illustrated state as Fig. 4, and locating sleeve 25 is empty.
Utilization is changed thermocouple pile 20 by the device of total mark 40 expressions with new thermocouple pile 50, and this device is following to be described with reference to Fig. 5 to 10.
In the illustrated exemplary embodiment of these Fig. 5 to Figure 10, and in about the described program of these figure, two thermocouple piles 20 are replaced, and new thermocouple pile 50 is 90 ° of layouts with respect to old thermocouple pile.
It is contemplated that other planform, for example, such as only changing a thermocouple pile.It is contemplated that also one or more new thermocouple piles are placed on the place of old one or more thermocouple piles.
As illustrated in Figures 5 and 6, more changing device 40 comprises an intermediate structure 41, and intermediate structure 41 is made of level and grid beam 42 that be fixed together.In the illustrated exemplary embodiment, intermediate structure 41 has the neighboring that is roughly rectangle in these figure, has supporting member 43 in its each corner, is used to be bearing in the upper surface of support plate 8.These supporting members 43 comprise the supporting leg that for example contains leveling board 44, and leveling board 44 is used to be pressed against the upper surface of support plate 8.Each leveling board 44 is porose 45, and hole 45 is used to make not shown fixed screw to pass through, and fixed screw is used to be connected to support plate 8.Each hole 45 is provided with a cup 46 that is used to prevent corresponding screw rotation.
In this Fig. 6, also can see, the grid of beam 42 is configured for the predefined paths of the top guide pipe 51 of fixing new thermopair, so that when the intermediate structure 41 of thermocouple pile 50 and top guide pipe 51 was equipped with in downward placement in advance, the free end lining 51a of each guide pipe 51 was consistent with the chosen in advance joint 22 on the support plate 8.The end of the free end of each top guide pipe 51 to being applied to cooperate with joint 22.
Before the intermediate structure 41 of putting down such prepackage, each previously selected joint 22, promptly each intends receiving the joint of new thermopair 58, the middle guide pipe 55 that is used to guide new thermopair 58 is installed, shown in Fig. 7 and 8.
According to illustrated first embodiment among Fig. 7, intervalve 55 is incorporated into simply to be responsible in 23.
This intervalve 55 is remained on by the Tapered Cup 55a that extends by edge 55b and is responsible in 23, and edge 55b seating is on the end of the cover 22a that forms in joint 22.Like this, intervalve 55 is freely placed to rotate freely in joint 22.
In this case, the joint 22 of each preliminary election is provided with one and connects bell-jar 60, this cover 60 comprises a hole 61 that is used to accept the lining 51a of respective upper guide pipe 51 on the one hand, comprises on the other hand being used to be locked at the device that the total marks 62 of usefulness in the joint 22 are represented.This device 62 that is used to be locked in the joint 22 is known, and is right-angled bend (quarter-turn) type, bayonet type or any other type.
According to a kind of not shown modification, extend as far as locking device 62 on the top of intervalve 55, and for example be fixed by welding on these devices.
According to an illustrated modification among Fig. 8, be used to guide the middle guide pipe 55 of new thermopair 58 to be placed in the bell-jar 60 with rotating freely.For this reason, as the embodiment of front, intervalve 55 comprises a Tapered Cup 55a who extends by edge 55b.Edge 55b seating is on the end in formed hole 61 in bell-jar 60 and be used to accept the lining 51a at place, respective upper guide pipe 51 ends.In this case, intervalve 55 is freely placed with rotation in bell-jar 60.
According to a not shown modification, intervalve 55 can for example be fixed by welding to bell-jar 60.
Bell-jar 60 also comprises the device 62 that is used to be locked in the joint 22.
The hole 61 of bell-jar 60 comprises the inlet 61a of a taper, and the lining 51a of corresponding top guide pipe 51 is inserted easily.This hole can comprise for example to be fixed by clip or the known fixed system of screwed lining 51a.
By the system that screwed fixes, for example comprise a not shown stopper.This stopper is screwed onto the top of bell-jar 60, and comprises the axial hole that a termination that is used to make top guide pipe 51 is passed through.This upper tube 51 is maintained in this hole by an abutment means or any other suitable structure.
More changing device 40 is placed on downwards on the support plate 8 of top in-pile component 6, carries out as following step.
Obviously, all operations carries out at a distance, and top in-pile component 6 is placed on downwards on the underwater operation platform 30.
At first, the pre-position on support plate 8 makes unshowned threaded hole, and the supporting member 43,47 and 48 of intermediate structure 41 will be located on these positions.Threaded hole for example produces by electrosparking (electrical discharge machining).
According to a preferred program (Fig. 7), will be used for guiding the middle guide pipe 55 of new thermopair 58 to be inserted into each previously selected joint 22.Guiding bell-jar 60 is installed and is utilized locking device 62 bell-jar 60 that will lead to be locked in the previously selected joint 22.
According to a modification (Fig. 8) of preferable procedure, after bell-jar 60 has located and be locked on the predetermined joint 22, the middle guide pipe 55 of new thermopair 58 is injected in the hole 61 of bell-jars 60.
According to a modification, middle guide pipe 55 and bell-jar 60 constitute independently assembly.In this case, they are installed on the previously selected joint 22 simultaneously.
By intermediate structure 41, the subassembly changing thermocouple pile 50 and be used to guide the top guide pipe 51 of new thermopair 58 to be constituted, be transported to worktable 30, progressively drop on the worktable 30, each sleeve 25 is placed in the centering device 47, as shown in Figure 9.
If top guide pipe 51 is arranged on the beam 42 of intermediate structure 41 in advance, the lining 51a of each top guide pipe 51 is consistent with previously selected joint 22, when middle structure 41 was being placed downwards, each lining 51a entered in the previously selected joint, and is extremely shown in Figure 9 as Fig. 7.
Each free end lining 51a can remain in the corresponding bell-jar 60 by fixed system, for example utilizes clip to fix or screw or any other any suitable system.
Preassembled like this intermediate structure 41 is placed on downwards on the upper surface of support plate 8, the not shown screw retention of these intermediate structure 41 usefulness, each screw is screwed in the supporting member 43,47 and 48 hole 45 of described intermediate structure 41.The top that each glass 46 driven in respective screws, loosening to prevent this screw work.
Next, new thermopair is slipped in each top guide pipe 51, corresponding to previously selected joint 22.The sensitive measurement end of each new thermopair 58 is positioned in a preposition place below the support plate 8 like this, will measure the temperature of the cooling medium of the group fuel assembly that leaves reactor core herein.
When changing thermocouple pile 50 and be positioned on the support plate 8, at the place, place of old thermocouple pile 20, the height of each abutment sleeve 25 is reduced, and for example uses electrosparking, so that replacing thermocouple pile 50 is located easily and thermopair is passed through easily.
If new thermopair is not introduced in the previously selected joint 22, for example because joint 22 or main guide pipe 23 are partly stopped up, the grid of beam 42 provides the path that changes this thermopair to reach the possibility of another joint 22 up to it.For this reason, top guide pipe 51 can the easy-off stationary installation be fixed on the beam 42 by known type.
By intermediate structure 41 the top in-pile component (Fig. 9) of at least one new thermocouple pile 50 and new thermopair 58 is installed, hangs out from worktable 30, and be put back in the container 1 of reactor.Then, reinstall top cover 1a, as shown in figure 10.
According to more changing device of the present invention, by preassembled intermediate structure, can at least one new thermocouple pile and new thermopair be installed with the operation of minimum number, therefore make the minimizing working time become possibility.
Claims (13)
1. the method for at least one thermocouple pile (20) in the top in-pile component (6) of changing nuclear reactor, described top in-pile component (6) comprises support plate (8), described support plate (8) has:
-be used to regulate the guide pipe (9) of the reactive cluster of reactor core;
-described at least one thermocouple pile (20), it comprise a cover thermopair and by in fixed on abutment sleeve (25); And
-joint (22), it is used to make described thermopair by described support plate (8),
It is characterized in that this method comprises the steps:
-described top in-pile component (6) is held in place under water the worktable (30),
-extract existing thermopair out;
Described at least one thermocouple pile (20) that-taking-up will be changed;
-by sleeve (25) intermediate structure (41) is located and is fixed on the described support plate (8), described intermediate structure (41) is equipped with at least one the replacing thermocouple pile (50) that is securely fixed on it, and described replacing thermocouple pile (50) prepackage is useful on the top guide pipe (51) of the new thermopair of guiding; Simultaneously, the free end lining (51a) with corresponding top guide pipe (51) is incorporated in each previously selected joint (22); And
-described intermediate structure is fixed on the described support plate; And
-new thermopair is incorporated in the corresponding top guide pipe (51), up to predetermined working position.
2. according to the method for claim 1, it is characterized in that, before described intermediate structure (41) being positioned on the described support plate (8), will be used for guiding the middle guide pipe (55) of new thermopair to be incorporated into each previously selected joint (22).
3. according to the method for claim 2, it is characterized in that, guide pipe (55) in the middle of described is locked onto on the described joint (22).
4. according to any one the method in the claim 1 to 3, it is characterized in that, before described intermediate structure (41) being positioned on the described support plate (8), this intermediate structure (41) is located and be fixed on to the top guide pipe (51) that will be used for new thermopair along predetermined path, make that the free end lining (51a) of each top guide pipe (51) overlaps with previously selected joint (22) when this intermediate structure (41) is placed on the described support plate (8) downwards.
5. according to any one the method in the claim 1 to 3, it is characterized in that, when described intermediate structure (41) was being placed downwards, described at least one replacing thermocouple pile (50) was placed on the pilot sleeve (25) that is associated with the thermocouple pile that will change (20).
6. according to the method for claim 5, it is characterized in that, before replacing thermocouple pile (50) is positioned, the length of pilot sleeve (25) is reduced.
7. the device of at least one thermocouple pile (20) in the top in-pile component (6) of changing nuclear reactor, described top in-pile component (6) comprises support plate (8), support plate (8) has:
-be used to regulate the guide pipe (9) of the reactive cluster of reactor core;
-described at least one thermocouple pile (20), it comprises a cover thermopair; And
-joint (22), it is used to make thermopair to pass through described support plate (8),
It is characterized in that, the device of at least one thermocouple pile (20) in the top in-pile component (6) of described replacing nuclear reactor comprises intermediate structure (41), described intermediate structure (41) is used for being placed on described support plate (8) downwards by supporting member (43,47,48) and goes up and be equipped with at least one the replacing thermocouple pile (50) that is securely fixed on it, and described replacing thermocouple pile (50) prepackage is useful on the top guide pipe (51) of the new thermopair of guiding.
8. according to the device of claim 7, it is characterized in that, described intermediate structure (41) is made of the grid of the horizontal beam that is fixed together (42), described horizontal beam (42) forms predetermined path, the described top guide pipe (51) that described predetermined path allows to be used for new thermopair is connected, so that when this structure (41) was placed on the support plate (8) downwards, the free end lining (51a) of each top guide pipe (51) overlapped with previously selected joint (22).
9. according to the device of claim 7 or 8, it is characterized in that, for each previously selected joint (22), this device comprises the middle guide pipe (55) that is used for new thermopair and is connected bell-jar (60), described connection bell-jar (60) comprises the hole (61) of the free end lining (51a) of accepting respective upper guide pipe (51) on the one hand, comprises the device (62) that is used to be locked in the joint (22) on the other hand.
10. according to the device of claim 9, it is characterized in that described middle guide pipe (55) is fixed on the described connection bell-jar (60).
11. the device according to claim 9 is characterized in that, the device (62) that guide pipe (55) in the middle of described is locked in the joint (22) is the right-angled bend type.
12. the device according to claim 9 is characterized in that, described connection bell-jar (60) comprises fixed system.
13. the device according to claim 12 is characterized in that, described fixed system is fixed by clip or the free end lining (51a) of the corresponding top of screwed guide pipe (51) works.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR0502495A FR2883096B1 (en) | 2005-03-14 | 2005-03-14 | METHOD AND ASSEMBLY FOR REPLACING AT LEAST ONE COLUMN OF THERMOCOUPLES OF INTERNAL EQUIPMENT SUPERIOR TO A NUCLEAR REACTOR |
| FR0502495 | 2005-03-14 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1841569A CN1841569A (en) | 2006-10-04 |
| CN1841569B true CN1841569B (en) | 2011-02-09 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2006100678424A Active CN1841569B (en) | 2005-03-14 | 2006-03-14 | Method and device for changing nuclear reactor upper component at least a thermoelectric couple column |
Country Status (2)
| Country | Link |
|---|---|
| CN (1) | CN1841569B (en) |
| FR (1) | FR2883096B1 (en) |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2915020B1 (en) * | 2007-04-12 | 2009-07-17 | Areva Np Sas | DEVICE AND METHOD FOR AUTOMATICALLY AND REMOTELY CONNECTING THE GUIDING DUCTS OF A THERMOCOUPLE OF INTERNAL EQUIPMENT EXCEEDING A NUCLEAR REACTOR |
| FR2949992B1 (en) * | 2009-09-16 | 2011-10-14 | Areva Np | DEVICE FOR AIDING WATER DURING THE EXTRACTION OR INSERTION OF AN ELONGATED SHAPE MEMBER IN A CONDUIT AND METHOD OF SUPPORTING THE EXTRACTION OR INSERTION OF SUCH AN ELEMENT. |
| US10438708B2 (en) * | 2011-10-04 | 2019-10-08 | Westinghouse Electric Company Llc | In-core instrument thimble assembly |
| FR2995438B1 (en) * | 2012-09-13 | 2014-10-10 | Areva Np | METHOD FOR REPLACING A GUIDE KEY FOR INTERNAL NUCLEAR REACTOR EQUIPMENT |
| FR3007811B1 (en) * | 2013-07-01 | 2015-07-31 | Areva Np | ASSEMBLY WITH A TUBE BLOCKING DEVICE, AND ASSOCIATED MAINTENANCE METHOD |
| FR3053515B1 (en) * | 2016-06-29 | 2018-08-17 | Areva Np | NUCLEAR REACTOR, METHODS FOR MOUNTING AND REPLACING THERMOCOUPLES CONDUITS, ASSEMBLY FOR IMPLEMENTING METHODS |
| CN108015490B (en) * | 2017-11-27 | 2019-05-24 | 广西防城港核电有限公司 | The method for blocking of thermocouple pile conduit |
| CN114589499B (en) * | 2020-12-03 | 2023-01-20 | 中核核电运行管理有限公司 | Reactor core thermocouple online replacement method |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2100496A (en) * | 1981-06-03 | 1982-12-22 | Westinghouse Electric Corp | Standard integrated head package |
| US4438649A (en) * | 1981-07-29 | 1984-03-27 | Electric Power Research Institute, Inc. | Apparatus for remotely positioning sensing devices in a reactor during operation thereof |
| FR2704679A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Pressurised water nuclear reactor comprising an anti-ejection retention device for vessel head penetration adapters |
| CN1104363A (en) * | 1993-02-03 | 1995-06-28 | 法玛通公司 | Device for the sealed clamping against a support surface of an instrumentation column |
| CN1123450A (en) * | 1994-09-09 | 1996-05-29 | 法玛通公司 | Sealing device for an instrumentation column penet rating the head of the vessel of a nuclear reactor inside an adapter |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB989167A (en) * | 1960-08-19 | 1965-04-14 | Babcock & Wilcox Ltd | Improvements in nuclear reactors |
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2005
- 2005-03-14 FR FR0502495A patent/FR2883096B1/en active Active
-
2006
- 2006-03-14 CN CN2006100678424A patent/CN1841569B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2100496A (en) * | 1981-06-03 | 1982-12-22 | Westinghouse Electric Corp | Standard integrated head package |
| US4438649A (en) * | 1981-07-29 | 1984-03-27 | Electric Power Research Institute, Inc. | Apparatus for remotely positioning sensing devices in a reactor during operation thereof |
| CN1104363A (en) * | 1993-02-03 | 1995-06-28 | 法玛通公司 | Device for the sealed clamping against a support surface of an instrumentation column |
| FR2704679A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Pressurised water nuclear reactor comprising an anti-ejection retention device for vessel head penetration adapters |
| CN1123450A (en) * | 1994-09-09 | 1996-05-29 | 法玛通公司 | Sealing device for an instrumentation column penet rating the head of the vessel of a nuclear reactor inside an adapter |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2883096A1 (en) | 2006-09-15 |
| CN1841569A (en) | 2006-10-04 |
| FR2883096B1 (en) | 2007-06-01 |
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