CN204857197U - Indirect neutron CT image device of weary fuel element of PWR - Google Patents
Indirect neutron CT image device of weary fuel element of PWR Download PDFInfo
- Publication number
- CN204857197U CN204857197U CN201520532081.XU CN201520532081U CN204857197U CN 204857197 U CN204857197 U CN 204857197U CN 201520532081 U CN201520532081 U CN 201520532081U CN 204857197 U CN204857197 U CN 204857197U
- Authority
- CN
- China
- Prior art keywords
- neutron
- fuel element
- spent fuel
- screen
- convert screen
- 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.)
- Withdrawn - After Issue
Links
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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a nuclear material check out test set. For the three -dimensional nondestructive test who realizes the weary fuel element of PWR, the utility model provides an indirect neutron CT image device of weary fuel element of PWR, the device is including weary fuel element motion control device and conversion screen exposure device, weary fuel element motion control device is including weary fuel element motion control ware and screening can, conversion screen exposure device includes neutron conversion screen, neutron conversion screen passageway, the neutron beam circulation is said and neutron conversion screen motion control ware, the neutron beam circulation is said and has still been opened weary fuel element entry. The utility model discloses an image device has realized the weary fuel element's of PWR three -dimensional nondestructive test, can obtain the complete detection information of defects such as weary fuel element pellet piece appearance, inside granule distributions of pellet, clad failure state, provides the powerful guarantee for china's pressurized -water core fuel element's quality testing and performance.
Description
Technical field
The utility model relates to a kind of nuclear material monitoring equipment, is specifically related to a kind of presurized water reactor spent fuel element indirect neutron CT imaging device.
Background technology
In nuclear industry field, for realizing the quality control of presurized water reactor nuclear fuel element, need to detect corresponding spent fuel element.But because presurized water reactor spent fuel element has hot, therefore general detection technique cannot be applied to it and detect.
Neutron-radiography is widely used in industrial circle as the Dynamic Non-Destruction Measurement of a kind of advanced person, has the plurality of advantages such as detection speed is fast, result is accurate, reliability is high.But the hot of presurized water reactor spent fuel element itself can produce severe jamming to neutron photography, cause cannot obtaining being detected as picture, therefore traditional neutron-radiography cannot directly apply to the detection of spent fuel element at all.
For this reason, current presurized water reactor spent fuel element neutron-radiography adopts indirect formation method, with neutron convert screen, image-forming information is converted, thus realize the qualitative detection of spent fuel element, the defect information such as spent fuel element pellet cracking, clad failure, involucrum hydrogen is poly-can be obtained.But the method only can complete the two-dimensional detection imaging of spent fuel element at present, the three-dimensional information of the defects such as spent fuel element pellet fragment pattern, the distribution of pellet internal particle, clad failure state therefore cannot be obtained.
Acquisition due to above-mentioned defect three-dimensional information depends on the three-dimensional values imaging of spent fuel element, but owing to still not having ripe three-dimensional values imaging device available at present, existing CT device also cannot be applicable to the three-dimensional values imaging of spent fuel element completely due to variety of problems, therefore the three dimensional lossless to realize presurized water reactor spent fuel element detects, and just needs to develop a kind of new imaging device.
Utility model content
For the three dimensional lossless realizing presurized water reactor spent fuel element detects, the utility model provides a kind of presurized water reactor spent fuel element indirect neutron CT imaging device.
This device comprises spent fuel element motion control device and conversion screen exposure device; Described spent fuel element motion control device comprises spent fuel element motion controller and screening can, and described spent fuel element motion controller comprises spent fuel element rotary electric machine and spent fuel element vertical moving motor; Described conversion screen exposure device comprises neutron convert screen, neutron convert screen passage, neutron streaming passage and neutron convert screen motion controller; Described neutron convert screen motion controller comprises neutron convert screen motion motor, neutron convert screen motion motor is connected with neutron convert screen by connecting rod, realizes the movement of neutron convert screen in neutron convert screen passage under the control of neutron convert screen motion controller; Described neutron streaming passage is used for the introducing of neutron streaming, and neutron streaming passage is connected with neutron convert screen passage; Neutron streaming passage also has spent fuel element entrance; Neutron convert screen passage and neutron streaming vias inner walls surface are laid with metal gadolinium.
Described spent fuel element rotary electric machine and spent fuel element vertical moving motor all adopt servomotor to be preferred.
Described neutron convert screen motion motor adopts servomotor to be preferred.
The design of presurized water reactor spent fuel element of the present utility model indirect neutron CT imaging device have employed CT reconstruction technique and the indirect formation method of neutron photography, the three dimension data reconstruct of presurized water reactor spent fuel element is carried out in multiple two-dimensional detection imagings continuous that can be obtained by automatic operation, avoids the radioactivity of spent fuel element itself to the impact being detected as picture.
For CT reconstruction technique, one of Major Difficulties of its three dimension data reconstruct is to guarantee that the imaging of each spent fuel element two-dimensional detection is accurately coaxial, otherwise cannot reconstruct three-dimensional values imaging clearly at all.For guaranteeing that two-dimensional detection imaging is coaxial, the utility model have employed fuel element motion controller and neutron convert screen motion controller accurately controls the rotation of fuel element and the movement of neutron convert screen respectively, ensure that the accuracy of motion control aspect.
But find in practical application, the accurate control only realizing motion aspect is still not enough to reconstruct three-dimensional values imaging clearly.After deliberation, in the indirect imaging process of neutron photography, comparatively significantly scattering can be there is in the neutron in neutron streaming, the neutron of scattering can cause the imaging area edge fog of two-dimensional detection imaging, therefore can have influence on the accuracy of interception position in the process of imaging area intercepting, and then affect the accurately coaxial of two-dimensional detection imaging.For this reason, the utility model is creationary have employed the method for laying metal gadolinium at neutron convert screen passage and neutron streaming vias inner walls surface, utilize metal gadolinium can sponge the neutron of scattering to the strong absorbent of neutron, thus the ill-defined problem in the imaging area solving two-dimensional detection imaging, ensure that the accurately coaxial of each spent fuel element two-dimensional detection imaging.
In sum, the three dimensional lossless that presurized water reactor spent fuel element of the present utility model indirect neutron CT imaging device achieves presurized water reactor spent fuel element detects, by carrying out the spent fuel element three-dimensional values imaging obtained analyzing the complete Detection Information that can obtain the defects such as spent fuel element pellet fragment pattern, the distribution of pellet internal particle, clad failure state, extend the Non-Destructive Testing quantity of information of presurized water reactor spent fuel element greatly, for the quality testing of China's presurized water reactor nuclear fuel element and performance boost provide powerful guarantee.
Accompanying drawing explanation
Fig. 1 presurized water reactor of the present utility model spent fuel element indirect neutron CT image device structure schematic diagram.
Fig. 2 conversion screen exposure device inner structure schematic diagram (overlooking).
Reference numeral: 1. spent fuel element motion control device, 2. conversion screen exposure device, 3. screening can, 4. spent fuel element motion controller, 5. spent fuel element, 6. neutron convert screen, 7. neutron streaming passage, 8. metal gadolinium, 9. spent fuel element entry position projection, 10. neutron convert screen passage, 11. neutron convert screen motion controllers, 12. metal gadoliniums.
Embodiment
Below in conjunction with accompanying drawing, embodiment of the present utility model is described further.
Embodiment
Adopt presurized water reactor spent fuel element of the present utility model indirect neutron CT imaging device to carry out three-dimensional values imaging to certain spent fuel element sample, its process is as follows:
Step one: this spent fuel element sample is moved in neutron streaming passage through spent fuel element entrance by spent fuel element motion controller;
Step 2: under the control of neutron convert screen motion controller, neutron convert screen is moved to spent fuel element sample rear by neutron convert screen passage;
Step 3: introduce neutron streaming by neutron streaming passage, neutron streaming obtains a width two-dimensional detection imaging after spent fuel element sample on neutron convert screen, removes neutron streaming;
Step 4: under the control of spent fuel element motion controller, spent fuel element sample is accurately rotated 1 degree, change neutron convert screen simultaneously;
Step 5: constantly repeat step 3 and step 4, until obtain the two-dimensional detection imaging adding up to 180 width;
Step 6: adopt CT reconstruction technique to carry out three-dimensional reconstruction to above-mentioned 180 width two-dimensional detection imagings, obtain the three-dimensional values imaging of this spent fuel element sample.
Imaging results shows: the spent fuel element sample three-dimensional values imaging definition obtained by said process is high, accurately can tell the Detection Information of the defects such as spent fuel element pellet fragment pattern, the distribution of pellet internal particle, clad failure state, also more existing two-dimensional detection formation method is more clear directly perceived for the defect information such as spent fuel element pellet cracking, involucrum hydrogen are poly-.Due to the employing of metal gadolinium, the 180 width two-dimensional detection imaging edges obtained are bright and sharp, are easy to the accurate intercepting realizing imaging area, obtain good effect.
Claims (3)
1. a presurized water reactor spent fuel element indirect neutron CT imaging device, is characterized in that: this device comprises spent fuel element motion control device and conversion screen exposure device; Described spent fuel element motion control device comprises spent fuel element motion controller and screening can, and described spent fuel element motion controller comprises spent fuel element rotary electric machine and spent fuel element vertical moving motor; Described conversion screen exposure device comprises neutron convert screen, neutron convert screen passage, neutron streaming passage and neutron convert screen motion controller; Described neutron convert screen motion controller comprises neutron convert screen motion motor, neutron convert screen motion motor is connected with neutron convert screen by connecting rod, realizes the movement of neutron convert screen in neutron convert screen passage under the control of neutron convert screen motion controller; Described neutron streaming passage is used for the introducing of neutron streaming, and neutron streaming passage is connected with neutron convert screen passage; Neutron streaming passage also has spent fuel element entrance; Neutron convert screen passage and neutron streaming vias inner walls surface are laid with metal gadolinium.
2. presurized water reactor spent fuel element indirect neutron CT imaging device as claimed in claim 1, is characterized in that: described spent fuel element rotary electric machine and spent fuel element vertical moving motor all adopt servomotor.
3. presurized water reactor spent fuel element indirect neutron CT imaging device as claimed in claim 1, is characterized in that: described neutron convert screen motion motor adopts servomotor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520532081.XU CN204857197U (en) | 2015-07-21 | 2015-07-21 | Indirect neutron CT image device of weary fuel element of PWR |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201520532081.XU CN204857197U (en) | 2015-07-21 | 2015-07-21 | Indirect neutron CT image device of weary fuel element of PWR |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204857197U true CN204857197U (en) | 2015-12-09 |
Family
ID=54747724
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201520532081.XU Withdrawn - After Issue CN204857197U (en) | 2015-07-21 | 2015-07-21 | Indirect neutron CT image device of weary fuel element of PWR |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN204857197U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105023622A (en) * | 2015-07-21 | 2015-11-04 | 中国原子能科学研究院 | Pressurized water reactor spent fuel element indirect neutron CT imaging device |
| CN111627585A (en) * | 2019-01-22 | 2020-09-04 | 中国原子能科学研究院 | Neutron monochromator shielding system |
-
2015
- 2015-07-21 CN CN201520532081.XU patent/CN204857197U/en not_active Withdrawn - After Issue
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105023622A (en) * | 2015-07-21 | 2015-11-04 | 中国原子能科学研究院 | Pressurized water reactor spent fuel element indirect neutron CT imaging device |
| CN105023622B (en) * | 2015-07-21 | 2018-01-19 | 中国原子能科学研究院 | A kind of indirect neutron CT imaging devices of presurized water reactor spent fuel element |
| CN111627585A (en) * | 2019-01-22 | 2020-09-04 | 中国原子能科学研究院 | Neutron monochromator shielding system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| KR101179540B1 (en) | Method for analyzing the Internal Density of Material using a X-ray Computerized Tomography | |
| CN105911077A (en) | Test method for XCT nondestructive detection of sulfate erosion damages of concrete material | |
| CN104730091A (en) | Gas turbine blade defects extraction and analysis method based on region segmenting detection | |
| CN204857197U (en) | Indirect neutron CT image device of weary fuel element of PWR | |
| CN105023622A (en) | Pressurized water reactor spent fuel element indirect neutron CT imaging device | |
| Yang et al. | Imaging and measuring methods for coating layer thickness of TRISO-coated fuel particles with high accuracy | |
| CN103817089A (en) | Automatic detection system and method for spherical fuel element fuel-free section | |
| CN104359763A (en) | Method for detecting internal crack developing of cement-based material under action of load | |
| CN105161147A (en) | Nondestructive testing method for spent fuel component of pressurized water reactor by virtue of three-dimensional neutron radiography | |
| CN106934856B (en) | Three-dimensional fault reconstruction and slice display method based on X-ray detection technology | |
| Bielecki et al. | Phillips-Tikhonov regularization with a priori information for neutron emission tomographic reconstruction on Joint European Torus | |
| Schrapp et al. | Artifact reduction in non-destructive testing by means of complementary data fusion of x-ray computed tomography and ultrasonic pulse-echo testing | |
| CN102243188B (en) | Platform and method for industrial computerized tomography (ICT) imaging, wireless streaming media data processing, and three dimensional reconstruction | |
| CN109870471A (en) | A kind of Cone-Beam CT angle sequence scattering acquisition methods of monochromatic light grid detecting | |
| CN105701847A (en) | Algebraic reconstruction method of improved weight coefficient matrix | |
| Zhu et al. | Uniformity assessment of TRISO fuel particle distribution in spherical HTGR fuel element using voronoi tessellation and delaunay triangulation | |
| CN108760776B (en) | Visual test method and system for water transmission in cement-based material | |
| CN204086173U (en) | A kind of fuel rod end plug weld seam detection plumbous cover of shielding | |
| CN210894172U (en) | X-ray small-angle scattering imaging system | |
| Tisseur et al. | Quality control of High Temperature Reactors (HTR) compacts via X-ray tomography | |
| JP2010185888A (en) | Radiation nondestructive inspection system and piping inspection method | |
| Zhang | Study on CT Image Reconstruction Applications in Industry | |
| CN118150616B (en) | Ray detection simulation method based on digital twinning | |
| CN114486957B (en) | Asphalt mixture microscopic structure testing method based on neutron imaging | |
| Hou et al. | A segmented γ scanning device and experimental research |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20151209 Effective date of abandoning: 20180119 |
|
| AV01 | Patent right actively abandoned |