CN206075844U - Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing - Google Patents
Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing Download PDFInfo
- Publication number
- CN206075844U CN206075844U CN201620990808.3U CN201620990808U CN206075844U CN 206075844 U CN206075844 U CN 206075844U CN 201620990808 U CN201620990808 U CN 201620990808U CN 206075844 U CN206075844 U CN 206075844U
- Authority
- CN
- China
- Prior art keywords
- gearshift
- collimator
- collimation
- cover plate
- industry
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
This utility model provides collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing, and the program includes cover plate, collimation body and gearshift；Cover plate is two panels, and collimation body is fixed between two panels cover plate and forms collimation mechanism；Collimation mechanism is arranged on gearshift；Gearshift can drive collimation mechanism transverse shifting and rotation.The program drives collimator mechanism kinematic using gearshift, disclosure satisfy that ray goes out the requirement of beam angle degree, disclosure satisfy that the relative geometry position relation of whole industrial CT system again.
Description
Technical field
The utility model relates to it is a kind of, especially collimate after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing
Device.
Background technology
Nuclear fuel（nuclear fuel）It is that, containing fissile nuclide, being placed on reactor interior energy makes self-holding nuclear fission chain type anti-
The material that should be achieved.Fuel element（fuel element）Be in reactor using nuclear fuel as the structure of main component on
Independent minimum component, its concrete shape have bar-shaped, tabular and spherical etc..Fuel assembly（fuel assembly）It is assembled in
The one group of fuel element do not taken apart together and in core loading and discharge process.
Fuel assembly is the core component of reactor, and fuel rod is the critical component of fuel assembly, wherein fuel rod bag
Shell is first that the anti-radioactivity in three road of nuclear power plant escapes barrier.Therefore the security reliability and economy of fuel rod, to reaction
The security reliability and economy of heap nuclear power plant operation is most important.This also illustrates that the operating experience of reactor fuel element is big
Focus mostly in the accumulation and summary of fuel rod operating experience, and with fuel rod breakage rate measuring reactor operation security reliability
Reason.
Since the fuel rod in reactor fuel assemblies and industrial products, so according to reliability rationale, it
The bathtub curve rule necessarily followed also in compliance with general industry product by crash rate or breakage rate in the whole phase in longevity, i.e., whole
The initial stage of individual phase in longevity and latter stage breakage rate are higher, and mid-term is relatively low.
Defect fuel rod, refers to that fuel rod occurs perforation (gap or pin hole), and fission product can be drained to cold by perforation
But, in agent, reactor operation is not affected by defective fuel rod.Burst slug rod refers to that the defect on fuel rod deteriorates, and occurs
Destroy compared with large perforation or involucrum, cause coolant circuit to stain.Defect fuel rod and burst slug rod are referred to as escape of fuel rod, tool
The fuel assembly for having escape of fuel rod is referred to as escape of fuel component.
Defect fuel rod and under the complicated environmental conditions such as high temperature, high pressure and strong Neutron Radiation Field, pellet in fuel rod
Swelling, deformation even can burst, the safe operation of serious Threat Reaction heap occurs.Understanding fuel assembly is in reactor
Change, the central cavity for studying fuel rod in the fuel assembly of high burnup form extremely important with the deformation of fuel rod.It is logical
Cross traditional detection method, such as metallography, detect fuel rod central cavity and crackle, need to take a significant amount of time, and need
The structure of destruction fuel assembly itself, it is impossible to detect the deformation of fuel rod.
Sigmatron Non-Destructive Testing can simply and quickly detect the structure inside fuel assembly, and expense is low, no
Waste is produced, is a kind of effective technological means.The design of collimator afterwards is crucial, should meet ray and go out wanting for beam angle degree
Ask, meet the relative geometry position relation of whole system again.
Utility model content
The purpose of this utility model, the deficiency being aiming at existing for prior art, and provide a kind of suitable for spentnuclear fuel
The technical scheme of collimator after the industry CT of rod Non-Destructive Testing, the program drive collimator mechanism kinematic, energy using gearshift
Enough meet the requirement that ray goes out beam angle degree, disclosure satisfy that the relative geometry position relation of whole industrial CT system again.
This programme is achieved by the following technical measures：
Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing, includes cover plate, collimation body and displacement dress
Put；Cover plate is two panels, and collimation body is fixed between two panels cover plate and forms collimation mechanism；Collimation mechanism is arranged on gearshift；
Gearshift can drive collimation mechanism transverse shifting and rotation.
As the preferred of this programme：Gearshift includes moving platform, silent flatform, motor, leading screw, drive shaft and rotation
Rotating shaft is held；Moving platform is arranged on silent flatform；Silent flatform bottom is fixed with motor and leading screw；Leading screw is connected with motor
Connect；Drive shaft is fixed on leading screw；Arc-shaped rail is provided with silent flatform；Swivel bearing is arranged in orbit；Drive shaft with
Moving platform is fixedly connected.
As the preferred of this programme：Drive shaft can be driven by leading screw and rotate and drive moving platform to rotate.
The beneficial effect of this programme can be learnt according to the narration to such scheme, due to adopting gearshift in this scenario
Collimator mechanism kinematic is driven, be disclosure satisfy that ray goes out the requirement of beam angle degree, be disclosure satisfy that the relative of whole industrial CT system again
Geometry site.
As can be seen here, this utility model compared with prior art, with substantive distinguishing features and progress, its beneficial effect implemented
Fruit is also obvious.
Description of the drawings
Structural representations of the Fig. 1 for collimation mechanism.
Structural representations of the Fig. 2 for gearshift.
In figure, 1 is cover plate, and 2 are defined stretched, and 3 is moving platform, and 4 is silent flatform, and 5 is swivel bearing, and 6 is drive shaft, and 7 are
Motor, 8 is leading screw.
Specific embodiment
Clearly to illustrate the technical characterstic of this programme, below by a specific embodiment, and its accompanying drawing is combined, it is right
This programme is illustrated.
By accompanying drawing as can be seen that this programme includes cover plate, collimation body and gearshift；Cover plate is two panels, collimates body
It is fixed between two panels cover plate and forms collimation mechanism；Collimation mechanism is arranged on gearshift；Gearshift can drive collimation
Mechanism's transverse shifting and rotation.Gearshift includes moving platform, silent flatform, motor, leading screw, drive shaft and rotary shaft
Hold；Moving platform is arranged on silent flatform；Silent flatform bottom is fixed with motor and leading screw；Leading screw is connected with motor；Drive
Moving axis is fixed on leading screw；Arc-shaped rail is provided with silent flatform；Swivel bearing is arranged in orbit；Drive shaft and moving platform
It is fixedly connected.Drive shaft can be driven by leading screw and rotate and drive moving platform to rotate.
Collimator mechanism kinematic is driven using gearshift in this programme, disclosure satisfy that ray goes out the requirement of beam angle degree, and
Disclosure satisfy that the relative geometry position relation of whole industrial CT system.
Preferred embodiment of the present utility model is the foregoing is only, it is not to limit this utility model, all at this
Any modification, equivalent and improvement made within the spirit and principle of utility model etc., should be included in this utility model
Protection domain within.
Claims (3)
1. collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing, is characterized in that：Include cover plate, collimation body and
Gearshift；The cover plate is two panels, and collimation body is fixed between two panels cover plate and forms collimation mechanism；The collimation mechanism is arranged
On gearshift；Institute's displacement apparatus can drive collimation mechanism transverse shifting and rotation.
2. collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing according to claim 1, is characterized in that：
Institute's displacement apparatus include moving platform, silent flatform, motor, leading screw, drive shaft and swivel bearing；The moving platform is arranged
On silent flatform；The silent flatform bottom is fixed with motor and leading screw；The leading screw is connected with motor；The driving
Axle is fixed on leading screw；Arc-shaped rail is provided with the silent flatform；The swivel bearing is arranged in orbit；The driving
Axle is fixedly connected with moving platform.
3. collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing according to claim 1, is characterized in that：
The drive shaft can be driven by leading screw and rotate and drive moving platform to rotate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620990808.3U CN206075844U (en) | 2016-08-31 | 2016-08-31 | Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620990808.3U CN206075844U (en) | 2016-08-31 | 2016-08-31 | Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN206075844U true CN206075844U (en) | 2017-04-05 |
Family
ID=58433779
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201620990808.3U Expired - Fee Related CN206075844U (en) | 2016-08-31 | 2016-08-31 | Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN206075844U (en) |
-
2016
- 2016-08-31 CN CN201620990808.3U patent/CN206075844U/en not_active Expired - Fee Related
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP5118297B2 (en) | Isotope generation method | |
| CA3040571C (en) | System and process for production and collection of radioisotopes | |
| CN103558293B (en) | Nuclear reactor pressure container bottom (head) girth joint ultrasonic inspection apparatus | |
| CN206075844U (en) | Collimator after a kind of industry CT suitable for spent fuel rods Non-Destructive Testing | |
| US20140192943A1 (en) | Fuel rod testing apparatus for nuclear fuel assembly | |
| JPS5950956B2 (en) | Method and device for positioning a leaking fuel rod in a nuclear fuel assembly | |
| CN201359858Y (en) | Source-loading rod of <252>Cf neutron-activated nuclear rod <235>U enrichment degree and uniformity detection unit | |
| Ge´ rard et al. | Situation of the baffle-former bolts in Belgian units | |
| KR102048540B1 (en) | Sampling device | |
| CN106808406A (en) | A kind of nuclear power station metallic graphite carbon sealing ring provision for disengagement | |
| CN111799011A (en) | Gamma radioactive source irradiator and transfer source-reversing device | |
| Kain | Damage Levels: Comparison of experiment and simulation | |
| US3842283A (en) | Method for determining the proportion of broken particles in the fuel compacts employed in high temperature reactors | |
| Gratchyov et al. | Demonstration experiment of 3 BN-600 MOX vibropac FAs irradiation for the excess weapons plutonium disposal | |
| JP4751849B2 (en) | Opening device for sealed container containing radioactive gas | |
| Xiaohui | Analysis and Research on Diagnosis Methods of AFA 3G Fuel Assembly Leakage | |
| Choo et al. | Development of dismantling techniques for irradiated HANARO instrumented capsule (03M-06U) in IMEF | |
| CN204988863U (en) | CT sample pull rod for universal testing machine under condition of hot laboratory cave | |
| JP2001091698A (en) | Radiation source assembly and compressor therefor | |
| Castanho et al. | Design and development of a device for the opening of irradiated aluminum capsules in the IPEN IEA-R1 nuclear reactor | |
| CN115331851A (en) | Nuclear fuel element for power transient test, test device and method | |
| Eyre | Industrial applications of radiation | |
| Choo et al. | Study on Dismantling technique of Jammed State between outer pipe and inner combined structure for HANARO Irradiated Instrumented Capsule (03M-06U) in IMEF | |
| BAY | Irradiation of LEU Targets in the BR2 Reactor for Mo-99 Production | |
| Jarousse et al. | CERCA Mo-99 annular cans target manufacturing development for ANSTO |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20180517 Address after: 621700 Huafeng new village, Jiangyou City, Mianyang, Sichuan Province, No. 9 Patentee after: INSTITUTE OF MATERIALS, CHINA ACADEMY OF ENGINEERING PHYSICS Address before: 621700 De Sheng Nan Road, Jiangyou City, Mianyang, Sichuan Province, No. 87 Patentee before: SICHUAN JUNENG NUCLEAR TECHNOLOGY ENGINEERING Co.,Ltd. |
|
| TR01 | Transfer of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20170405 Termination date: 20210831 |
|
| CF01 | Termination of patent right due to non-payment of annual fee |