CN213958604U - A excessive rule detection device for nuclear fuel assembly - Google Patents
A excessive rule detection device for nuclear fuel assembly Download PDFInfo
- Publication number
- CN213958604U CN213958604U CN202022891282.2U CN202022891282U CN213958604U CN 213958604 U CN213958604 U CN 213958604U CN 202022891282 U CN202022891282 U CN 202022891282U CN 213958604 U CN213958604 U CN 213958604U
- Authority
- CN
- China
- Prior art keywords
- nuclear fuel
- fuel assembly
- over
- gauge
- clamping
- 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.)
- Active
Links
Images
Classifications
-
- 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
Abstract
The utility model relates to a nuclear fuel assembly detects technical field, especially an excessive rule detection device for nuclear fuel assembly, first clamping part and second clamping part enclose into the measurement space who is used for measuring nuclear fuel assembly, the both ends of first clamping part can be dismantled with the tip that the second clamping part corresponds respectively and be connected, after nuclear fuel assembly's partly measurement space that stretches into, first clamping part can be followed the first direction and taken off nuclear fuel assembly, the second clamping part can be followed the second direction and taken off nuclear fuel assembly, the equal perpendicular to nuclear fuel assembly of first direction and second direction falls into the direction of first excessive rule. The utility model provides a cross rule detection device for nuclear fuel assembly, the significantly reduced is behind the card shell, because of first cross rule and nuclear fuel assembly relative movement once more along the damaged condition emergence's of nuclear fuel assembly probability again of the orientation of nuclear fuel assembly motion, reduces the probability that causes huge economic loss.
Description
Technical Field
The utility model relates to a nuclear fuel assembly detects technical field, especially a cross rule detection device for nuclear fuel assembly.
Background
When the nuclear fuel assembly is detected by the over gauge, sometimes the nuclear fuel assembly is clamped with the over gauge, and then the nuclear fuel assembly reversely exits from the over gauge, so that the nuclear fuel assembly is easily damaged, and huge economic loss is caused.
SUMMERY OF THE UTILITY MODEL
The utility model aims to provide a: the over-regulation detection device for the nuclear fuel assembly is provided for solving the problems that the nuclear fuel assembly is reversely withdrawn from the over-regulation, the nuclear fuel assembly is easily damaged and huge economic loss is caused in the prior art.
In order to realize the purpose, the utility model discloses a technical scheme be:
an over-gauge detection device for a nuclear fuel assembly comprises a first over-gauge, wherein the first over-gauge comprises a first clamping part and a second clamping part, a measuring space for measuring the nuclear fuel assembly is enclosed by the first clamping part and the second clamping part, two ends of the first clamping part are detachably connected with the corresponding end parts of the second clamping part respectively,
and the first and second clamping portions are configured to: after some of nuclear fuel assembly stretched into nuclear fuel assembly's measurement space, first clamping part can be followed first direction and detached nuclear fuel assembly, the second clamping part can be followed the second direction and detached nuclear fuel assembly, first direction with the second direction all is perpendicular to nuclear fuel assembly falls into the direction of first rule of crossing.
The application a cross rule detection device for nuclear fuel assembly, first clamping part with the second clamping part encloses into first cross rule and is used for measuring nuclear fuel assembly's measurement space, after nuclear fuel assembly's some stretched into nuclear fuel assembly's measurement space, if the card shell condition appears, then dismantle first clamping part and second clamping part each other to transversely break away from with nuclear fuel assembly along first direction and second direction respectively, the significantly reduced is behind the card shell, because of first cross rule and nuclear fuel assembly along the damaged probability of the condition emergence of nuclear fuel assembly relative movement once more of the direction of nuclear fuel assembly motion, reduce the probability that causes huge economic loss.
Preferably, at least one end of the first clamping portion is provided with a groove portion, the groove portion is provided with at least two positioning surfaces, the second clamping portion is correspondingly provided with a protruding portion, the protruding portion is provided with an arc surface portion, and the arc surface portion is in contact with all the positioning surfaces.
Through the positioning fit of the cambered surface part and the at least two corresponding positioning surfaces, the line fit is formed, and therefore the fit precision is improved.
Preferably, two positioning surfaces are arranged on the groove portion, an included angle is formed between the two positioning surfaces, and the included angle is (0 degrees and 180 degrees).
Preferably, the two locating surfaces are perpendicular to each other.
Preferably, a second over gauge is further included, the second over gauge being located below the first over gauge, the second over gauge being used to measure a lower portion of the nuclear fuel assembly.
Preferably, still include the base, first rule and second rule of crossing all set up on the base.
Preferably, the first clamping portion is connected with the base.
Preferably, the base is a structural member made of stone. The base is the structure of making by the stone material to reduce the deformation that causes because of the temperature variation, thereby improve the detection precision of first rule and second rule.
Preferably, at least one second clamping mechanism for clamping the nuclear fuel assembly is arranged between the first over gauge and the second over gauge.
To sum up, owing to adopted above-mentioned technical scheme, the beneficial effects of the utility model are that:
1. the utility model provides a cross rule detection device for nuclear fuel assembly, first clamping part with the second clamping part encloses into first cross rule and is used for measuring nuclear fuel assembly's measurement space, after nuclear fuel assembly's some stretched into nuclear fuel assembly's measurement space, when the card shell condition appears, then dismantle first clamping part and second clamping part each other to transversely break away from with nuclear fuel assembly along first direction and second direction respectively, the significantly reduced is behind the card shell, because of first cross rule and nuclear fuel assembly along the damaged probability of the condition emergence of nuclear fuel assembly relative movement once more of the direction of nuclear fuel assembly motion, reduce the probability that causes huge economic loss.
2. The utility model provides a cross rule detection device for nuclear fuel assembly, through two at least locating surface location fit that cambered surface portion and its correspond, form the line cooperation to improve its complex precision.
3. The utility model provides an excessive rule detection device for nuclear fuel assembly, the structure that the base was made by the stone material to reduce the deformation that causes because of temperature variation, thereby improve the alignment accuracy of first excessive rule and second excessive rule and follow-up retaining mechanism and hoist.
Drawings
Fig. 1 is a schematic front view of the structure of the over-gauge detection device of the present application.
Fig. 2 is a left side view of the structure of the over-gauge detecting device of the present application.
Fig. 3 is a schematic top view of the structure of the over-gauge detection apparatus of the present application (with the nuclear fuel assembly in the over-rail assembly position).
Fig. 4 is a schematic top view of the structure of the over-gauge detecting apparatus of the present application (with the nuclear fuel assembly in the temporary storage position).
Fig. 5 is a cross-sectional view a-a of fig. 1 of the present application.
Fig. 6 is an enlarged view of the portion I in fig. 5 of the present application.
FIG. 7 is a cross-sectional view B-B of FIG. 1 of the present application.
FIG. 8 is a cross-sectional view C-C of FIG. 1 of the present application.
Fig. 9 is an enlarged view of section II in fig. 8 of the present application.
Fig. 10 is a cross-sectional view D-D in fig. 4 of the present application.
The labels in the figure are: 1-underframe, 11-temporary storage seat, 12-roller assembly, 13-first clamping mechanism, 2-support frame, 21-base, 3-rotary suspension arm, 31-sling, 32-rotary lower support, 33-rotary upper support, 34-first reversing pulley assembly, 341-pulley I, 342-pulley support, 343-fine adjustment mechanism, 344-support plate, 35-driving mechanism, 351-driving wheel, 352-driven wheel, 353-connecting piece, 354-rotary handle, 36-second reversing pulley assembly, 37-counterweight II, 4-over-gauge assembly, 401-first over-gauge, 402-second over-gauge, 41-first clamping part, 410-groove part, 411-positioning surface, 42-second clamping part, 420-bulge, 421-arc part, 5-winch, 51-wire rope, 52-tension measuring part, 53-reel, 54-counterweight one, 55-lifting handle, 6-follow-up support mechanism, 61-first support frame, 611-first roller, 612-groove part, 613-, 62-second support frame, 621-second roller, 622-bulge part, 7-second slewing bearing, 71-outer bearing, 72-inner bearing, 73-positioning block, 8-second clamping mechanism and 9-nuclear fuel assembly.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings.
In order to make the objects, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the invention.
Example 1
As shown in fig. 5 and 6, the over-gauge detecting device for a nuclear fuel assembly according to the present embodiment includes a first over-gauge 401, where the first over-gauge 401 includes a first clamping portion 41 and a second clamping portion 42, the first clamping portion 41 is fixedly connected to the support frame 2, the first clamping portion 41 and the second clamping portion 42 enclose a measuring space for measuring a nuclear fuel assembly 9, two ends of the first clamping portion 41 are detachably connected to corresponding ends of the second clamping portion 42,
and the first and second clamping portions 41 and 42 are configured to: after a part of the nuclear fuel assembly 9 extends into the measuring space of the nuclear fuel assembly 9, the first clamping portion 41 can be detached from the nuclear fuel assembly 9 along the first direction, the second clamping portion 42 can be detached from the nuclear fuel assembly 9 along the second direction, and the first direction and the second direction are both perpendicular to the nuclear fuel assembly 9 and fall into the direction of the first over gauge 401.
Preferably, at least one end of the first clamping portion 41 is provided with a groove portion 410, at least two positioning surfaces 411 are provided on the groove portion 410, a protrusion portion 420 is correspondingly provided on the second clamping portion 42, an arc surface portion 421 is provided on the protrusion portion 420, and the arc surface portion 421 contacts with all the positioning surfaces 411.
The arc surface 421 is matched with at least two corresponding positioning surfaces 411 in a positioning way to form a line matching, so that the matching precision is improved.
Preferably, two positioning surfaces 411 are arranged on the groove portion 410, and an included angle is formed between the two positioning surfaces 411, and the included angle is 0 ° and 180 °.
Preferably, the two positioning surfaces 411 are perpendicular to each other.
Preferably, a second over gauge 402 is further included, the second over gauge 402 being located below the first over gauge 401, the second over gauge 402 being used for measuring the lower portion of the nuclear fuel assembly 9.
Preferably, a base 21 is arranged on the support frame 2, the base 21 is a structural member made of stone, and the gauge assembly 4 is connected with the base 21.
The base 21 is a structural member made of stone to reduce deformation due to temperature change, thereby improving the alignment accuracy of the first and second over gauges 401 and 402 with the servo support mechanism 6 and the hanger 31.
Preferably, at least one second clamping mechanism 8 for clamping the nuclear fuel assembly 9 is arranged between the first over gauge 401 and the second over gauge 402.
The beneficial effects of this embodiment: the utility model provides an excessive rule detection device for nuclear fuel assembly, first clamping part 41 with second clamping part 42 encloses into first excessive rule 401 and is used for measuring the measurement space of nuclear fuel assembly 9, after some stretches into the measurement space of nuclear fuel assembly 9, if the card shell condition appears, dismantle first clamping part 41 and second clamping part 42 each other to transversely break away from with nuclear fuel assembly 9 along first direction and second direction respectively, the significantly reduced is behind the card shell, because of first excessive rule 401 and nuclear fuel assembly 9 relative movement once more along the direction of nuclear fuel assembly 9 motion lead to the probability that the condition that nuclear fuel assembly 9 was destroyed takes place, reduce the probability that causes huge economic loss.
Example 2
As shown in fig. 1 to 9, the over-regulation detecting apparatus for a nuclear fuel assembly according to the present embodiment includes an over-regulation detecting device for a nuclear fuel assembly according to embodiment 1.
The over-regulation detection device of the nuclear fuel assembly 9 comprises in particular,
a support frame 2;
the over-gauge assembly 4 is used for measuring a nuclear fuel assembly 9, and the over-gauge assembly 4 is connected with the support frame 2;
the rotary suspension arm 3 is connected with the support frame 2 and can horizontally rotate, a lifting appliance 31 for lifting the nuclear fuel assembly 9 is arranged on the rotary suspension arm 3, the rotary suspension arm 3 has an idle state and a measuring state on a rotary path, and when the rotary suspension arm 3 is in the measuring state, the over-gauge assembly 4 is positioned below the lifting appliance 31;
and the winch 5 is used for lifting the lifting appliance 31, and a steel wire rope 51 led out from the winch 5 is connected with the lifting appliance 31.
The whole system is supported by the support frame 2, when measurement is carried out, the nuclear fuel assembly 9 is hoisted by the hoisting device 31, the hoisting device 31 is hoisted by the winch 5, the nuclear fuel assembly 9 is further hoisted to the required height, the rotary hoisting arm 3 is in an idle state at the moment, then the rotary hoisting arm 3 horizontally rotates to a measurement state, the nuclear fuel assembly 9 stops to the corresponding position above the gauge passing assembly 4 after rotating, at the moment, the hoisting device 31 descends by releasing the steel wire rope 51 through the winch 5, and then the nuclear fuel assembly 9 descends and enters the gauge passing assembly 4 to be measured.
In the process, the nuclear fuel assembly 9 is effectively lifted and horizontally rotated through machinery and is placed into the over-gauge assembly 4 from top to bottom, so that the nuclear fuel assembly 9 is transferred and measured.
A tension measuring component 52 is connected between the hanger 31 and the steel wire rope 51, the tension measuring component 52 can effectively measure the tension borne by the steel wire rope 51 in the process that the nuclear fuel assembly 9 enters the over-gauge assembly 4, and when the tension measuring component 52 detects that the tension borne by the steel wire rope 51 is suddenly and rapidly reduced, the nuclear fuel assembly 9 is clamped by the over-gauge assembly 4 and the nuclear fuel assembly 9 is unqualified.
The tension measuring means 52 is preferably a tension measuring instrument.
The spreader 31 is located outside the support frame 2.
The lower part of the support frame 2 is further provided with a first counterweight 54, the winch 5 comprises a winding drum 53, and one end, far away from the lifting appliance 31, of the steel wire rope 51 is connected with the first counterweight 54 after bypassing the winding drum 53.
The nuclear fuel assembly 9 is heavy, so that the steel wire rope 51 bears large tension, the required tension capable of being borne by the winch 5 is also large, one end of the steel wire rope 51 far away from the lifting appliance 31 bypasses the winding drum 53 and is connected with the counterweight I54, the counterweight I54 balances the dead weight of the nuclear fuel assembly 9, the bearing load of the winch 5 is effectively reduced, the bearing requirement of the winch 5 is reduced, the purpose of lifting the nuclear fuel assembly 9 can be achieved through the smaller winch 5, and the cost increased by the arrangement of the counterweight I54 is far less than the cost saved by the reduction of the type of the winch 5.
The winch 5 further comprises a lifting handle 55, the lifting handle 55 is arranged at the lower part of the support frame 2, and the lifting handle 55 can drive the winding drum 53 to rotate positively and negatively.
Specifically, a pulley mechanism is arranged between the lifting handle 55 and the winding drum 53, and the lifting handle 55 drives the winding drum 53 to rotate forward and backward through the pulley mechanism.
The swing arm 3 further comprises a swing lower bearing 32 and a swing upper bearing 33 which are mutually connected in a swing mode, the swing lower bearing 32 is connected with the support frame 2, and the lifting appliance 31 can rotate together with the swing upper bearing 33.
The upper slewing bearing 33 is pivoted relative to the lower slewing bearing 32 to drive the spreader 31 to rotate together, thereby driving the nuclear fuel assembly 9 to rotate together with the spreader 31.
The lower slewing bearing 32 is located on top of the support frame 2. Thereby ensuring that the whole device is lower in height under the requirement of lifting and transporting the nuclear fuel assembly 9.
The slewing upper bearing 33 is provided with a first reversing pulley assembly 34, the first reversing pulley assembly 34 is used for reversing the steel wire rope 51, the first reversing pulley assembly 34 is positioned above the lifting appliance 31, and the steel wire rope 51 led out from the winch 5 is connected with the lifting appliance 31 after bypassing the first reversing pulley assembly 34.
The first diverting pulley assembly 34 includes a first pulley 341 and a pulley bracket 342 for mounting the first pulley 341, and the first diverting pulley assembly 34 further includes a fine adjustment mechanism 343 for adjusting the pulley bracket 342 to move radially along the slewing upper bearing 33.
Through the fine adjustment mechanism 343, can adjust the distance of first switching pulley assembly 34 to the centre of rotation of slewing upper bearing 33 to reach the distance of adjustment hoist 31 to the centre of rotation of slewing upper bearing 33, and then reach the purpose of fine setting the distance of nuclear fuel assembly 9 to the centre of rotation of slewing upper bearing 33, make nuclear fuel assembly 9 well centering over rule subassembly 4.
As shown in fig. 10, a supporting plate 344 is connected to the pulley bracket 342, a through hole in threaded engagement with the fine adjustment mechanism 343 is formed in the supporting plate 344, the fine adjustment mechanism 343 penetrates through the supporting plate 344 and is rotatably connected to the pulley bracket 342, the pulley bracket 342 can move along with the fine adjustment mechanism 343, and the fine adjustment mechanism 343 is in threaded engagement with the supporting plate 344, so that when the fine adjustment mechanism 343 rotates relative to the supporting plate 344, the fine adjustment mechanism 343 can move along the thickness direction of the supporting plate 344, and further the pulley bracket 342 can be driven to move along with the fine adjustment mechanism 343, so as to achieve fine adjustment of the first pulley 341.
The slewing upper support 33 is provided with a second reversing pulley assembly 36, the second reversing pulley assembly 36 is used for reversing the steel wire rope 51, the second reversing pulley assembly 36 is positioned at the slewing center of the slewing upper support 33, and the steel wire rope 51 led out of the winch 5 is connected with the lifting appliance 31 after sequentially bypassing the first reversing pulley assembly 34 and the second reversing pulley assembly 36.
And a second counterweight 37 is arranged on the slewing upper bearing 33 on the side opposite to the first reversing pulley assembly 34.
The second counterweight 37 is used for balancing at least a part of gravity bending moment applied to the rotary upper support 33 by the nuclear fuel assembly 9.
The follow-up retaining mechanism 6 can coaxially and synchronously rotate with the rotary suspension arm 3, the follow-up retaining mechanism 6 is positioned below the lifting appliance 31, and the follow-up retaining mechanism 6 is in rotary connection with the support frame 2.
When the lifting appliance 31 lifts the nuclear fuel assembly 9 to rotate, the lower part of the nuclear fuel assembly 9 is a free end, the nuclear fuel assembly 9 swings due to inertia force, the lifting safety risk of the lifting appliance 31 can be increased, moreover, the nuclear fuel assembly 9 collides with the support frame 2 due to too large swinging, the nuclear fuel assembly 9 is damaged, and great loss is caused, meanwhile, when the lifting appliance 31 swings to the upper part of the over-gauge assembly 4, the time from swinging to standing of the nuclear fuel assembly 9 is long, the preparation time for testing the over-gauge assembly 4 can be prolonged, and the testing efficiency is reduced.
When the lifting appliance 31 lifts the nuclear fuel assembly 9, the follow-up support mechanism 6 supports the nuclear fuel assembly 9 to prevent the nuclear fuel assembly 9 from swinging, and meanwhile, the follow-up support mechanism 6 can coaxially and synchronously rotate with the rotary suspension arm 3, so that the follow-up support mechanism 6 can always support the nuclear fuel assembly 9 in the rotation process of the nuclear fuel assembly 9, the swinging condition in the rotation process of the nuclear fuel assembly 9 is avoided, and the lifting safety risk of the lifting appliance 31 is reduced; avoiding major losses due to collisions between the nuclear fuel assembly 9 and the support frame 2; and the preparation time of the over-gauge component 4 is greatly reduced, and the testing efficiency is improved.
The follow-up support mechanism 6 is rotatably connected with the support frame 2 through a second rotary support 7, the second rotary support 7 comprises an outer support 71 and an inner support 72, the outer support 71 and the inner support 72 mutually rotate through a rotary gear ring, the inner support 72 is connected with the support frame 2, and the outer support 71 is connected with the follow-up support mechanism 6.
The follow-up support mechanism 6 comprises a first support frame 61 and a second support frame 62, one end of the first support frame 61 is hinged to the outer support 71, the other end of the first support frame 61 is detachably connected with one end of the second support frame 62, the other end of the second support frame 62 is hinged to the outer support 71, and a first clamping space for clamping the nuclear fuel assembly 9 is arranged between the first support frame 61 and the second support frame 62.
The first supporting frame 61 is provided with at least one first roller 611, the second supporting frame 62 is provided with at least one second roller 621, and all the first rollers 611 and all the second rollers 621 form the first clamping space.
The second roller 621 and/or the first roller 611 are preferably polyethylene rollers.
The number of the second rollers 621 is two, and the two second rollers 621 are disposed on one side of the second protective frame 62 close to the first protective frame 61.
The number of the first rollers 611 is two, and both are disposed on one side of the first holder 61 close to the second holder 62.
The driving mechanism 35 is used for driving the upper slewing bearing 33 and the lower slewing bearing 32 to relatively rotate, the driving mechanism 35 comprises a driving wheel 351 and a driven wheel 352, the driving wheel 351 drives the driven wheel 352 to rotate through a connecting piece 353, the driven wheel 352 is located on the lower slewing bearing 32, the driving wheel 351 is located at the lower part of the support frame 2, a transmission assembly is matched between the output end of the driven wheel 352 and the upper slewing bearing 33, and the driven wheel 352 can drive the upper slewing bearing 33 to rotate relative to the lower slewing bearing 32 through the transmission assembly.
Preferably, the transmission assembly is a turbine worm transmission. The linkage 353 is preferably a timing belt,
a rotary handle 354 is coaxially connected to the driving wheel 351, and the rotary handle 354 is located at the lower part of the supporting frame 2. So as to be convenient for the operation of the personnel.
At least one positioning block 73 for limiting the rotation of the outer support 71 is arranged on the inner support 72.
The positioning block 73 can be used to rotatably support the outer support 71 at a predetermined position, which makes it easier to position the nuclear fuel assembly 9 during rotation.
The end of the first support frame 61 far from the outer support 71 is provided with a groove portion 612, the groove portion 612 is arranged on one side of the first support frame 61 close to the second support frame 62, and the second support frame 62 is provided with a protrusion portion 622 matched with the groove portion 612.
The recessed portion 612 has a frame-shaped structure, and the protruding portion 622 is a triangular protruding portion.
Through line positioning, the accuracy is higher compared with surface positioning.
The over-gauge assembly 4 comprises a first over-gauge 401, the first over-gauge 401 comprises a first clamping portion 41 and a second clamping portion 42, the first clamping portion 41 is fixedly connected with the support frame 2, the first clamping portion 41 and the second clamping portion 42 enclose a measuring space for measuring the nuclear fuel assembly 9, two ends of the first clamping portion 41 are detachably connected with corresponding ends of the second clamping portion 42, and the first clamping portion 41 and the second clamping portion 42 are configured to: after a part of the nuclear fuel assembly 9 extends into the measuring space of the nuclear fuel assembly 9, the first clamping part 41 can be separated from the nuclear fuel assembly 9 along the first direction, the second clamping part 42 can be separated from the nuclear fuel assembly 9 along the second direction, the first direction and the second direction are perpendicular to the nuclear fuel assembly 9 and fall into the direction of the first over gauge 401, and the design is carried out, so that the nuclear fuel assembly 9 can be conveniently taken out when being clamped by the over gauge assembly 4, and the fuel assembly is not damaged.
The first clamping portion 41 and the second clamping portion 42 enclose a first over gauge 401 for measuring a measuring space of the nuclear fuel assembly 9, after a part of the nuclear fuel assembly 9 extends into the measuring space of the nuclear fuel assembly 9, if a clamping situation occurs, the first clamping portion 41 and the second clamping portion 42 are mutually detached and transversely separated from the nuclear fuel assembly 9 along the first direction and the second direction respectively, and the probability of the occurrence of the situation that the nuclear fuel assembly 9 is damaged due to relative movement of the first over gauge 401 and the nuclear fuel assembly 9 again along the moving direction of the nuclear fuel assembly 9 after the clamping is greatly reduced.
At least one end of the first clamping portion 41 is provided with a groove portion 410, the groove portion 410 is provided with at least two positioning surfaces 411, the second clamping portion 42 is correspondingly provided with a protruding portion 420, the protruding portion 420 is provided with an arc surface portion 421, and the arc surface portion 421 contacts with all the positioning surfaces 411.
The arc surface 421 is matched with at least two corresponding positioning surfaces 411 in a positioning way to form a line matching, so that the matching precision is improved.
The groove portion 410 is provided with two positioning surfaces 411, an included angle is formed between the two positioning surfaces 411, and the included angle is 0 degree and 180 degrees.
The included angle is preferably [60 °,120 °, and more preferably 90 °, i.e. the two positioning surfaces 411 are perpendicular to each other.
The over-gauge assembly 4 further comprises a second over-gauge 402, the second over-gauge 402 being located below the first over-gauge 401, the second over-gauge 402 being used for measuring a lower portion of the nuclear fuel assembly 9.
The support frame 2 is provided with a base 21, the base 21 is a structural member made of stone, and the gauge passing assembly 4 is connected with the base 21.
The base 21 is a structural member made of stone to reduce deformation due to temperature change, thereby improving the alignment accuracy of the first and second over gauges 401 and 402 with the servo support mechanism 6 and the hanger 31.
At least one second clamping mechanism 8 is arranged between the first over gauge 401 and the second over gauge 402, and the specific structure of the second clamping mechanism 8 refers to the follow-up holding mechanism 6.
The bottom of the support frame 2 is provided with a bottom frame 1, the bottom frame 1 is of a cross structure, a temporary storage seat 11 is arranged on the bottom frame 1, a first clamping mechanism 13 used for clamping the nuclear fuel assembly 9 is arranged above the temporary storage seat 11, the temporary storage seat 11 and the first clamping mechanism 13 support the nuclear fuel assembly 9 stably, and the specific structure of the first clamping mechanism 13 refers to the follow-up protection mechanism 6.
And the buffer 11 is configured to: when the swing boom 3 is in an idle state, the temporary storage 11 is located below the spreader 31.
The bottom of the bottom frame 1 is provided with a plurality of roller assemblies 12 for moving the bottom frame 1.
The above description is only exemplary of the present invention and should not be taken as limiting the scope of the present invention, as any modifications, equivalents, improvements and the like made within the spirit and principles of the present invention are intended to be included within the scope of the present invention.
Claims (9)
1. An over-gauge detection device for a nuclear fuel assembly, characterized by: the nuclear fuel assembly gauge comprises a first over gauge (401), wherein the first over gauge (401) comprises a first clamping part (41) and a second clamping part (42), a measuring space for measuring a nuclear fuel assembly (9) is enclosed by the first clamping part (41) and the second clamping part (42), two ends of the first clamping part (41) are detachably connected with corresponding ends of the second clamping part (42) respectively,
and the first clamping portion (41) and the second clamping portion (42) are configured to: after a part of the nuclear fuel assembly (9) stretches into the measuring space of the nuclear fuel assembly (9), the first clamping part (41) can be separated from the nuclear fuel assembly (9) along a first direction, the second clamping part (42) can be separated from the nuclear fuel assembly (9) along a second direction, and the first direction and the second direction are perpendicular to the nuclear fuel assembly (9) and fall into the direction of the first over gauge (401).
2. An over-regulation detection device for a nuclear fuel assembly according to claim 1, characterized in that: at least one end of the first clamping portion (41) is provided with a groove portion (410), the groove portion (410) is provided with at least two positioning surfaces (411), the second clamping portion (42) is correspondingly provided with a protruding portion (420), the protruding portion (420) is provided with an arc surface portion (421), and the arc surface portion (421) is in contact with all the positioning surfaces (411).
3. An over-regulation detection device for a nuclear fuel assembly according to claim 2, characterized in that: the groove part (410) is provided with two positioning surfaces (411), an included angle is formed between the two positioning surfaces (411), and the included angle is (0 degree and 180 degrees).
4. An over-regulation detection device for a nuclear fuel assembly according to claim 3, characterized in that: the two positioning surfaces (411) are perpendicular to each other.
5. An over-regulation detection device for a nuclear fuel assembly according to any one of claims 1 to 4, characterized in that: and the device also comprises a second over gauge (402), wherein the second over gauge (402) is positioned below the first over gauge (401), and the second over gauge (402) is used for measuring the lower part of the nuclear fuel assembly (9).
6. An over-regulation detection device for a nuclear fuel assembly according to claim 5, characterized in that: the device further comprises a base (21), and the first over gauge (401) and the second over gauge (402) are arranged on the base (21).
7. An over-regulation detection device for a nuclear fuel assembly according to claim 6, characterized in that: the first clamping portion (41) is connected with the base (21).
8. An over-regulation detection device for a nuclear fuel assembly according to claim 6, characterized in that: the base (21) is a structural member made of stone.
9. An over-regulation detection device for a nuclear fuel assembly according to claim 6, characterized in that: at least one second clamping mechanism (8) for clamping a nuclear fuel assembly (9) is arranged between the first over gauge (401) and the second over gauge (402).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022891282.2U CN213958604U (en) | 2020-12-03 | 2020-12-03 | A excessive rule detection device for nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022891282.2U CN213958604U (en) | 2020-12-03 | 2020-12-03 | A excessive rule detection device for nuclear fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN213958604U true CN213958604U (en) | 2021-08-13 |
Family
ID=77213910
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202022891282.2U Active CN213958604U (en) | 2020-12-03 | 2020-12-03 | A excessive rule detection device for nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN213958604U (en) |
-
2020
- 2020-12-03 CN CN202022891282.2U patent/CN213958604U/en active Active
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN213958604U (en) | A excessive rule detection device for nuclear fuel assembly | |
| CN213958603U (en) | Follow-up protection device for nuclear fuel assembly over-regulation detection assembly | |
| CN112556527B (en) | A excessive rule check out test set for nuclear fuel assembly | |
| CN218145506U (en) | Rotating device suitable for crawler crane superlift hoisting | |
| CN115112484B (en) | Bridge jib tensile strength testing arrangement | |
| CN112775873A (en) | Overhauling platform | |
| CN211954643U (en) | Simulation test device for bow-shaped plate torque limiter | |
| CN108342989A (en) | A kind of auxiliary support apparatus and bridge rotating system | |
| CN208167555U (en) | A kind of auxiliary support apparatus and bridge rotating system | |
| CN201330124Y (en) | Deviation rectification and turning device for sling of crane | |
| CN205684705U (en) | S-shaped ladle turret structure | |
| CN208195261U (en) | Hot continuous rolling coiling machine upper sleeve apparatus | |
| CN208906929U (en) | Double sided slider bar column examines anti-gravity charging manipulator | |
| CN217350632U (en) | Dynamic weighing device for forklift | |
| CN207498006U (en) | A kind of adjustable modularization hanging basket of center of gravity | |
| CN218156662U (en) | Balanced heavy check out test set of hoist | |
| CN214667230U (en) | Automatic hanging code checking mechanism of belt scale | |
| CN213201837U (en) | Cantilever swinging device of middle-pulling pay-off machine | |
| CN219038389U (en) | Window glass lifter slider check out test set | |
| CN218665002U (en) | Flexibly-rotating hook group structure form | |
| CN215766851U (en) | Crankshaft crank neck parallelism detection device | |
| CN220154166U (en) | Vertical wire rope sling torque measuring device | |
| CN212982235U (en) | Automatic unhooking mechanism of lifting appliance | |
| CN215711631U (en) | Marine overlength cylinder class equipment turning device | |
| CN216549352U (en) | Cantilever crane |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant |