CN213958603U - Follow-up protection device for nuclear fuel assembly over-regulation detection assembly - Google Patents

Abstract

The utility model relates to a fuel rod test technical field, especially a follow-up is protected and is supported device for nuclear fuel assembly crosses rule determine module, including follow-up support mechanism and second slewing bearing, follow-up support mechanism is used for centre gripping nuclear fuel assembly, second slewing bearing includes the outer support and the inner support of mutual swing joint, outer support with follow-up support mechanism is connected. According to the follow-up supporting device for the nuclear fuel assembly over-regulation detection assembly, in the rotation process, the follow-up supporting mechanism always supports the nuclear fuel assembly to prevent the nuclear fuel assembly from swinging, so that the swinging condition in the rotation process of the nuclear fuel assembly is avoided, and the hoisting safety risk of a lifting appliance is reduced; and avoid the major loss caused by collision between supporting arm and the nuclear fuel assembly; and the preparation time of the over-gauge assembly test is greatly reduced, and the test efficiency is improved.

Description

Follow-up protection device for nuclear fuel assembly over-regulation detection assembly

Technical Field

The utility model relates to a fuel rod test technical field, especially a follow-up is protected and is held device for nuclear fuel assembly crosses rule testing component.

Background

Utilize hoist and gyration davit to carry, when gyration removed nuclear fuel subassembly, nuclear fuel subassembly lower part is the free end, the wobbling condition can appear because of inertial force in the nuclear fuel subassembly, this can increase the hoist and mount safety risk of hoist, moreover, the too big collision of nuclear fuel subassembly and support frame can be caused to the swing, lead to the nuclear fuel subassembly to damage, cause great loss, simultaneously, when the hoist swings to crossing rule subassembly top, the nuclear fuel subassembly is very long by the time of swinging to static, can prolong the preparation time of crossing rule subassembly test, reduce the efficiency of test.

SUMMERY OF THE UTILITY MODEL

The utility model aims to provide a: when the existing nuclear fuel assembly rotates and moves, the nuclear fuel assembly is collided with the support frame due to overlarge swing, so that the nuclear fuel assembly is damaged; and the time from the swing to the rest of the nuclear fuel assembly is long, so that the efficiency of the test is reduced.

In order to realize the purpose, the utility model discloses a technical scheme be:

a follow-up support device for a nuclear fuel assembly over-regulation detection assembly comprises a follow-up support mechanism and a second rotary support, wherein the follow-up support mechanism is used for clamping the nuclear fuel assembly, the second rotary support comprises an outer support and an inner support which are mutually and rotatably connected, and the outer support is connected with the follow-up support mechanism.

According to the follow-up support device for the nuclear fuel assembly over-regulation detection assembly, when a lifting appliance and a rotary suspension arm are used for lifting and rotating to move a nuclear fuel assembly, an inner support is arranged below the rotary suspension arm and is coaxial with the rotary suspension arm, when the follow-up support device is used, the follow-up support mechanism is used for clamping the nuclear fuel assembly, and the outer support is connected with the follow-up support mechanism; and avoid the major loss caused by collision between supporting arm and the nuclear fuel assembly; and the preparation time of the over-gauge assembly test is greatly reduced, and the test efficiency is improved.

Preferably, the follow-up support mechanism comprises a first support frame and a second support frame, one end of the first support frame is hinged to the outer support, the other end of the first support frame is detachably connected with one end of the second support frame, the other end of the second support frame is hinged to the outer support, and a first clamping space for clamping the nuclear fuel assembly is arranged between the first support frame and the second support frame.

Preferably, the first supporting frame is provided with at least one first roller, the second supporting frame is provided with at least one second roller, and all the first rollers and all the second rollers enclose the first clamping space.

Preferably, the number of the second rollers is two, and the two second rollers are arranged on one side of the second protection frame close to the first protection frame.

Preferably, the two second rollers are arranged perpendicular to each other.

Preferably, at least one of the first rollers is disposed in parallel with at least one of the second rollers.

Preferably, the number of the first rollers is two, and the two first rollers are arranged on one side of the first protection frame close to the second protection frame.

Preferably, the end of the first protective frame far away from the outer support is provided with a groove portion, the groove portion is arranged on one side of the first protective frame close to the second protective frame, and the second protective frame is provided with a protruding portion matched with the groove portion.

Preferably, the groove portion is a frame-shaped structure, and the protrusion portion is a triangular protrusion portion.

Through line positioning, the accuracy is higher compared with surface positioning.

Preferably, at least one positioning block for limiting the rotation over-position of the outer support is arranged on the inner support.

The rotation over-position means that the outer support rotates relative to the inner support beyond a preset position.

Through the positioning block, the preset position of the outer support rotary support can be realized, and the nuclear fuel assembly is easier to position during rotation.

Preferably, the outer bearing and the inner bearing are rotationally connected to each other by a rotary ring gear.

To sum up, owing to adopted above-mentioned technical scheme, the beneficial effects of the utility model are that:

1. according to the follow-up retaining device for the nuclear fuel assembly over-regulation detection assembly, the follow-up retaining mechanism always retains the nuclear fuel assembly to prevent the nuclear fuel assembly from swinging, so that the swinging condition in the rotation process of the nuclear fuel assembly is avoided, and the hoisting safety risk of a lifting appliance is reduced; and avoid the major loss caused by collision between supporting arm and the nuclear fuel assembly; and the preparation time of the over-gauge assembly test is greatly reduced, and the test efficiency is improved.

2. The utility model provides a follow-up is protected and is held device for nuclear fuel assembly crosses rule determine module, concave part is frame column structure, the bellying is the triangle convex part, through the line location, for the face location, its precision is higher.

3. The utility model provides a follow-up is protected and is supported device for nuclear fuel assembly crosses rule determine module, through the locating piece, can make the outer support gyration support preset position, is the easier location when its nuclear fuel assembly gyration.

Drawings

Fig. 1 is a schematic structural front view of an over-gauge detection assembly according to the present application.

Fig. 2 is a left side view of the structure of the over-gauge detecting assembly of the present application.

FIG. 3 is a schematic top view of the structure of the over gauge detection assembly of the present application (with the nuclear fuel assembly in the over-rail assembly position).

Fig. 4 is a schematic top view of the over-gauge detection assembly of the present application (with the nuclear fuel assembly in the staging seat 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. 8 to 9, the follow-up support device for the nuclear fuel assembly over-regulation detecting assembly according to the present embodiment includes a follow-up support mechanism 6 and a second rotary support 7, wherein the follow-up support mechanism 6 is used for clamping the nuclear fuel assembly 9, the second rotary support 7 includes an outer support 71 and an inner support 72 which are rotatably connected with each other, 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.

In addition, in a more preferable mode, two second rollers 621 are provided, and both are provided on a side of the second holder 62 close to the first holder 61.

In addition, in a more preferable mode, the two second rollers 621 are disposed perpendicular to each other.

In addition, it is further preferable that at least one of the first rollers 611 is disposed in parallel with at least one of the second rollers 621.

In addition to the above, it is further preferable that two first rollers 611 are provided, and both are provided on a side of the first holder 61 close to the second holder 62.

In addition to the above, it is further preferable that a groove portion 612 is provided at an end portion of the first holder 61 away from the outer support 71, the groove portion 612 is provided at a side of the first holder 61 close to the second holder 62, and a protrusion portion 622 fitted to the groove portion 612 is provided at the second holder 62.

In addition to the above, it is further preferable that the recessed portion 612 has a frame-like structure, and the protruding portion 622 has a triangular protruding portion.

Through line positioning, the accuracy is higher compared with surface positioning.

In addition to the above, it is further preferable that at least one positioning block 73 for limiting the rotation over position of the outer support 71 is provided on the inner support 72.

Over-rotation means that outer bearing 71 rotates past a predetermined position relative to inner bearing 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 outer bearing 71 and the inner bearing 72 are rotationally connected to each other by a rotary ring gear.

The beneficial effects of this embodiment: when the following protection device for the nuclear fuel assembly over-regulation detection assembly is used for lifting and rotating the nuclear fuel assembly 9 by using the lifting appliance 31 and the rotating suspension arm 3, the inner support 72 is arranged below the swing boom 3 and is arranged coaxially with the swing boom 3, in use, the follower support 6 is used to hold the nuclear fuel assembly 9, and the outer support 71 is connected to the follower support 6, when the rotary suspension arm 3 rotates to move the nuclear fuel assembly 9, the outer support 71 and the inner support 72 synchronously rotate relatively, thereby achieving the purpose that the rotary suspension arm 3 and the follow-up support mechanism 6 coaxially rotate synchronously, during the rotation, the follow-up support mechanism 6 always supports the nuclear fuel assembly 9 to prevent the nuclear fuel assembly 9 from swinging, thereby avoiding the swinging condition in the rotation process of the nuclear fuel assembly 9 and reducing the hoisting safety risk of the hoisting tool 31; and avoid the major loss caused by collision 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.

Example 2

As shown in fig. 1 to 10, the over-regulation detecting assembly for a nuclear fuel assembly according to the present embodiment includes a follow-up supporting device for a nuclear fuel assembly over-regulation detecting assembly according to embodiment 1,

the nuclear fuel assembly over-regulation detection assembly specifically comprises,

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 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.

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 (10)

1. A follow-up is protected and is held device for nuclear fuel assembly crosses rule detection subassembly which characterized in that: the device comprises a follow-up support mechanism (6) and a second rotary support (7), wherein the follow-up support mechanism (6) is used for clamping a nuclear fuel assembly (9), the second rotary support (7) comprises an outer support (71) and an inner support (72) which are mutually and rotatably connected, and the outer support (71) is connected with the follow-up support mechanism (6).

2. The follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 1, characterized in that: follow-up is protected and is held mechanism (6) including first protection frame (61) and second and is protected support (62), the one end of first protection frame (61) with outer support (71) are articulated mutually, the other end of first protection frame (61) with the connection can be dismantled to the one end of second protection frame (62), the other end of second protection frame (62) with outer support (71) are articulated mutually, first protection frame (61) with be provided with the first centre gripping space that is used for centre gripping nuclear fuel assembly (9) between second protection frame (62).

3. A follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 2, characterized in that: 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 a first clamping space in a surrounding mode.

4. A follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 3, characterized in that: the number of the second rollers (621) is two, and the two second rollers are arranged on one side, close to the first protective frame (61), of the second protective frame (62).

5. The follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 4, characterized in that: the two second rollers (621) are arranged perpendicular to each other.

6. A follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 3, characterized in that: at least one of the first rollers (611) is disposed in parallel with at least one of the second rollers (621).

7. A follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 3, characterized in that: the number of the first rollers (611) is two, and the first rollers are arranged on one side, close to the second holding frame (62), of the first holding frame (61).

8. A follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 2, characterized in that: the end part, far away from the outer support (71), of the first protection support (61) is provided with a groove part (612), the groove part (612) is arranged on one side, close to the second protection support (62), of the first protection support (61), and a protruding part (622) matched with the groove part (612) is arranged on the second protection support (62).

9. The follow-up support device for a nuclear fuel assembly over-regulation detection assembly according to claim 8, characterized in that: the groove part (612) is of a frame-shaped structure, and the protruding part (622) is a triangular protruding part.

10. A follow-up support device for a nuclear fuel assembly over-regulation detecting assembly according to any one of claims 1 to 6, characterized in that: the inner support (72) is provided with at least one positioning block (73) for limiting the rotation over-position of the outer support (71).

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