CA2488318A1 - Dimensional measurement and inspection system of candu fuel bundle in-bay of candu power plant - Google Patents
Dimensional measurement and inspection system of candu fuel bundle in-bay of candu power plant Download PDFInfo
- Publication number
- CA2488318A1 CA2488318A1 CA002488318A CA2488318A CA2488318A1 CA 2488318 A1 CA2488318 A1 CA 2488318A1 CA 002488318 A CA002488318 A CA 002488318A CA 2488318 A CA2488318 A CA 2488318A CA 2488318 A1 CA2488318 A1 CA 2488318A1
- Authority
- CA
- Canada
- Prior art keywords
- nuclear fuel
- fuel bundle
- linear variable
- variable measurement
- measurement sensors
- 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.)
- Granted
Links
Classifications
-
- 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
- G21C17/102—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain the sensitive element being part of a fuel element or a fuel assembly
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- 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
Provided is a dimensional measurement and inspection system of a CANDU nuclear fuel bundle in a water chamber (reception bay) of a Heavy water nuclear reactor. In the system, a dimension measuring unit measures a dimension (i.e., surface profile of fuel rod, diameter and length of fuel bundle, end plate waviness of fuel bundle, circumferential profile of fuel bundle) of the nuclear fuel bundle by using a plurality of linear variable measurement sensors (LVDT) . An inspecting unit inspects a surface of the nuclear fuel bundle through a radiation tolerant camera. A
control unit automatically processes a variety of data and image data, which are provided from the dimension measuring unit and the inspecting unit, by using a control computer.
The system accurately measures and inspects the nuclear fuel bundle in air or water to output its resultant values.
control unit automatically processes a variety of data and image data, which are provided from the dimension measuring unit and the inspecting unit, by using a control computer.
The system accurately measures and inspects the nuclear fuel bundle in air or water to output its resultant values.
Claims (20)
1. A dimensional measurement and inspection system of a CANDU fuel bundle in air or water chamber (reception bay) of a heavy water nuclear reactor, the system comprising:
a dimension measuring unit for measuring a dimension of the nuclear fuel bundle by using a plurality of linear variable measurement sensors (LVDT);
an inspecting unit for inspecting a surface of tree nuclear fuel bundle through a radiation tolerant camera; and a control unit for automatically processing a variety of data and image data, which are provided from the dimension measuring unit and the inspecting unit, by using a control computer, whereby the nuclear fuel bundle is accurately measured and inspected in air or water to output its resultant values.
a dimension measuring unit for measuring a dimension of the nuclear fuel bundle by using a plurality of linear variable measurement sensors (LVDT);
an inspecting unit for inspecting a surface of tree nuclear fuel bundle through a radiation tolerant camera; and a control unit for automatically processing a variety of data and image data, which are provided from the dimension measuring unit and the inspecting unit, by using a control computer, whereby the nuclear fuel bundle is accurately measured and inspected in air or water to output its resultant values.
2. The system according to claim 1, wherein the dimension measuring unit and the inspecting unit are positioned on a predetermined sized support plate, frames are upwardly protruded from both corners of the support plate, and a hook frame is disposed at a center of the frame to hang on a hook of a crane.
3. The system according to claim 1, wherein the dimension measuring unit 10 has a rotary unit on which the nuclear fuel bundle is putted and rotated, and the rotary unit has a rotary motor, a driving pulley connected to a shaft of the rotary motor, an infinite-loop type first belt loaded on the driving pulley, a plurality of first driven pulleys, second driven pulleys corresponding to the first driven pulleys, a second belt loaded on the second driven pulleys, and a lower third driven pulley, such that when the nuclear fuel bundle are loaded at the left and right sides on the first and second belts 26a and 26b, the nuclear fuel bundle is rotated on the first and second belts due to the operation of the rotary motor.
4. The system according to claim 1, wherein the dimension measuring unit further comprises a position adjusting unit for adjusting left and right positions of the nuclear fuel bundle putted on the first and second belts, the position adjusting unit comprises a plurality of rotary cylinders and a rod having an end for mounting a pusher block thereon, and a plurality of rollers are mounted on the pusher block to provide a pushing force without damaging end plates of the nuclear fuel bundle such that the plurality of rollers pull the nuclear fuel bundle to adjust the position of the nuclear fuel bundle.
5. The system according to claim 4, wherein the position adjusting unit allows the plurality of rollers to pull the nuclear fuel bundle during the rotation of the nuclear fuel bundle on the first and second belts, thereby minimizing a local abrasion when the nuclear fuel bundle is moved.
6. The system according to claim 1, wherein the dimension measuring unit further comprises a length and profile measuring unit for measuring a length and a profile of the nuclear fuel bundle, and the length and profile measuring unit comprises a plurality of linear variable measurement sensors, double-acting pneumatic cylinders for moving the linear variable measurement sensors to the left and right in a lengthwise direction of the nuclear fuel bundle on the rotary unit, and rotating motors for rotating the linear variable measurement sensors in a circumferential direction of the nuclear fuel bundle.
7. The system according to claim 6, wherein the linear variable measurement sensors (LVDT) are fixed on a holder in a row to be arranged at a center of the nuclear fuel bundle and a center of each ring of the nuclear fuel bundle, and wherein when the linear variable measurement sensors are rotated one time, they are turned one time around end plates provided at both sides of the nuclear fuel bundle.
8. The system according to claim 6, wherein the double-acting pneumatic cylinder has a moving member movably fitted to a guide on a slide base, and the rotating motor is mounted on the moving member to rotate the linear variable measurement sensors in the circumferential direction of the nuclear fuel bundle, and the double-acting pneumatic cylinder moves the linear variable measurement sensors in the lengthwise direction of the nuclear fuel bundle.
9. The system according to claim 1, wherein the dimension measuring unit further comprises a diameter and profile measuring unit for measuring a diameter of the nuclear fuel bundle and detecting a profile of the nuclear fuel rod, and the diameter and profile measuring unit comprises a pair of linear variable measurement sensors disposed to horizontally face each other at front and rear sides of the nuclear fuel bundle, a fixing member for allowing the linear variable measurement sensors to traverse the nuclear fuel bundle and to be disposed at the front and rear sides of the nuclear fuel bundle, and a transfer motor, a guide rail and a ball screw for moving the fixing member in the lengthwise direction of the nuclear fuel bundle.
10. The system according to claim 9, wherein the diameter and profile measuring unit further comprises a reference setting sensor, and the reference setting sensor is disposed to allow an interval between the reference setting sensor and the linear variable measurement sensors to correspond to intervals between maximal outer diameters of the nuclear fuel rods respectively contacting with the reference setting sensor and the linear variable measurement sensors, such that when the reference setting sensor detects at its touch rod a maximal diameter of any one outer nuclear fuel rod of the nuclear fuel bundle, the linear variable measurement sensors are disposed to respectively correspond to the maximal outer diameters of the nuclear fuel rods being in contact with the linear variable measurement sensors.
11. The system according to claim 9, wherein the fixing member comprises front and rear sensor mounts, and wherein the front sensor mount has a vertical straight-line type structure for horizontally mounting the linear variable measurement sensor, and the rear sensor mount is constructed to have a slant portion (S) at its middle side and a straight-line portion (Sa) at its lower side to allow the linear variable measurement sensor to be selectively mounted at different slant angles.
12. The system according to claim 11, wherein if the nuclear fuel rods are 37 (37-element fuel bundle) in number, the linear variable measurement sensors of the sensor mounts are horizontally mounted to face each other, and if the nuclear fuel rods are 43 (CANFLEX fuel bundle) in number, the linear variable measurement sensor is horizontally mounted on the one sensor mount and the linear variable measurement sensor is aslant mounted on the slant portion (S) of the other sensor mount.
13. The system according to claim 1, wherein the inspecting unit comprises a first driving motor and a left and right moving block for moving the camera in the lengthwise direction of the nuclear fuel bundle, the left and right moving block comprises a front and rear moving block and a second driving motor disposed to be vertical to the movement direction of the left and right moving block on its upper plane, and the radiation tolerant camera is mounted on the front and rear moving block to access to the nuclear fuel bundle in the lengthwise direction of the nuclear fuel bundle through an activation of the first driving motor and in the diameter (radius) direction of the nuclear fuel bundle through an activation of the second driving motor.
14. The system according to claim 13, wherein the first driving motor has a rotary shaft connected to one end of the ball screw, the ball screw is disposed along a pair of first shaft rails disposed in the lengthwise direction of the nuclear fuel bundle, and the left and right moving block is screwed into the ball screw to move the camera in the lengthwise direction of the nuclear fuel bundle through the activation of the first driving motor.
15. The system according to claim 13, wherein the second driving motor has a rotary shaft for mounting a pinion gear thereon, and the pinion gear is geared into a fixed rack gear along a second shaft rail at one side of the left and right moving block such that when the second driving motor is activated, the radiation tolerant camera can be moved in the diameter (radius) direction of the nuclear fuel bundle.
16. The system according to claim 13, wherein the inspecting unit has a plurality of mirrors at an opposite side of the camera to indirectly photograph the end plates, which are not directly photographed by the camera, thereby preventing a blind spot.
17. The system according to claim 16, wherein the mirror has an angle controlling plate for controlling a mount angle to incline a mirror surface in up and down directions of the nuclear fuel bundle, and the angle controlling plate has a plurality of circular arc-shaped holes for joint screws.
18. The system according to claim 1, wherein the control unit comprises:
a sensor control unit electrically connected to each of the linear variable measurement sensors and the reference setting sensor to control operations of the linear variable measurement sensors and the reference setting sensor, and receiving and processing a signal from the linear variable measurement sensors and the reference setting sensor;
a motor control unit for controlling the motors and the double-acting pneumatic cylinders to move the linear variable measurement sensors to a desired position; and an image control unit for collecting and processing images photographed by the camera.
a sensor control unit electrically connected to each of the linear variable measurement sensors and the reference setting sensor to control operations of the linear variable measurement sensors and the reference setting sensor, and receiving and processing a signal from the linear variable measurement sensors and the reference setting sensor;
a motor control unit for controlling the motors and the double-acting pneumatic cylinders to move the linear variable measurement sensors to a desired position; and an image control unit for collecting and processing images photographed by the camera.
19. The system according to claim 1, wherein the control unit comprises a displaying unit having an inspection image monitor and a control-state displaying monitor for providing and outputting processed detected values and measured values to external workers, and the control unit has an image recorder and a personal computer to transmit and store a variety of measured values and detected values.
20. The system according to any one of claims 1 to 17, wherein the linear variable measurement sensors, the reference setting sensor, the motors, the cylinder and the camera all have a watertight structure to be operated in atmosphere or in the water chamber (W) (reception bay) of the Heavy water nuclear reactor.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR1020040052870A KR100622264B1 (en) | 2004-07-08 | 2004-07-08 | Dimensional measurement and inspection system of candu fuel bundle in-bay of candu power plant |
| KR2004-52870 | 2004-07-08 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CA2488318A1 true CA2488318A1 (en) | 2006-01-08 |
| CA2488318C CA2488318C (en) | 2012-01-10 |
Family
ID=35610411
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA2488318A Expired - Fee Related CA2488318C (en) | 2004-07-08 | 2004-11-23 | Dimensional measurement and inspection system of candu fuel bundle in-bay of candu power plant |
Country Status (2)
| Country | Link |
|---|---|
| KR (1) | KR100622264B1 (en) |
| CA (1) | CA2488318C (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102867553A (en) * | 2011-07-08 | 2013-01-09 | 韩电原子力燃料株式会社 | Apparatus for measuring outer diameters of fuel rods of nuclear fuel assembly |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100775577B1 (en) * | 2006-06-16 | 2007-11-12 | 한전원자력연료 주식회사 | Automated welding equipment and method for the guide thimble plug of the guide thimble tube in the nuclear fuel assembly |
| KR101002628B1 (en) * | 2008-08-28 | 2010-12-20 | 두산중공업 주식회사 | Apparatus for automatically overlay welding, inspecting and processing nozzzle part having different kind metals of pressurizer in nuclear power plant and method thereof |
| KR102044441B1 (en) * | 2017-09-29 | 2019-11-13 | 유저스(주) | Apparatus for measuring data of nuclear fuel tube assembly and a method using the device |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4195411A (en) | 1978-04-25 | 1980-04-01 | Westinghouse Electric Corp. | Remote gaging apparatus |
| JP3059386B2 (en) | 1996-06-27 | 2000-07-04 | 日本ニユクリア・フユエル株式会社 | Nuclear fuel rod length measuring device |
| KR100287325B1 (en) | 1998-06-24 | 2001-04-16 | 장인순 | Nuclear Fuel Bundle Serial Number Recognition Device after Use |
| JP2000009880A (en) | 1998-06-24 | 2000-01-14 | Hitachi Ltd | Device and method for inspecting fuel assembly |
| JP2000258583A (en) | 1999-03-05 | 2000-09-22 | Nuclear Fuel Ind Ltd | Measuring device for fuel rod gap in boiling water reactor fuel assembly |
| KR200239421Y1 (en) | 2001-04-30 | 2001-10-12 | 케이앤티(주) | Manipulator for damage nuclear fuel inspection equipment |
-
2004
- 2004-07-08 KR KR1020040052870A patent/KR100622264B1/en not_active IP Right Cessation
- 2004-11-23 CA CA2488318A patent/CA2488318C/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102867553A (en) * | 2011-07-08 | 2013-01-09 | 韩电原子力燃料株式会社 | Apparatus for measuring outer diameters of fuel rods of nuclear fuel assembly |
| CN102867553B (en) * | 2011-07-08 | 2016-09-21 | 韩电原子力燃料株式会社 | The nuclear fuel rod external diameter measuring device of nuclear fuel assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| KR20060004034A (en) | 2006-01-12 |
| KR100622264B1 (en) | 2006-09-14 |
| CA2488318C (en) | 2012-01-10 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EEER | Examination request | ||
| MKLA | Lapsed |
Effective date: 20171123 |