CN105023622A - Pressurized water reactor spent fuel element indirect neutron CT imaging device - Google Patents

Pressurized water reactor spent fuel element indirect neutron CT imaging device Download PDF

Info

Publication number
CN105023622A
CN105023622A CN201510431174.8A CN201510431174A CN105023622A CN 105023622 A CN105023622 A CN 105023622A CN 201510431174 A CN201510431174 A CN 201510431174A CN 105023622 A CN105023622 A CN 105023622A
Authority
CN
China
Prior art keywords
neutron
fuel element
spent fuel
screen
water reactor
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
Application number
CN201510431174.8A
Other languages
Chinese (zh)
Other versions
CN105023622B (en
Inventor
陈东风
刘蕴韬
魏国海
韩松柏
贺林峰
武梅梅
王洪立
王雨
孙凯
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN201510431174.8A priority Critical patent/CN105023622B/en
Publication of CN105023622A publication Critical patent/CN105023622A/en
Application granted granted Critical
Publication of CN105023622B publication Critical patent/CN105023622B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)

Abstract

The invention relates to a nuclear material detection device. The invention provides a pressurized water reactor spent fuel element indirect neutron CT imaging device. The device realizes a 3D nondestructive test on a pressurized water reactor spent fuel element. The device comprises a spent fuel element motion control device and a conversion screen exposure device. The spent fuel element motion control device comprises a spent fuel element motion controller and a shield housing. The conversion screen exposure device comprises a neutron convert screen, a neutron convert screen channel, a neutron beam channel and a neutron convert screen motion controller. The neutron beam channel is provided with a spent fuel element inlet. The imaging device realizes a 3D nondestructive test on a pressurized water reactor spent fuel element, can acquire complete detection information of defects such as spent fuel element core fragment morphology, core inner particle distribution and a housing breaking state, and can provide forceful guarantee for quality detection and performance improvement of a pressurized water reactor spent fuel element in China.

Description

A kind of presurized water reactor spent fuel element indirect neutron CT imaging device
Technical field
The present invention relates to a kind of nuclear material monitoring equipment, be 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.
Summary of the invention
For the three dimensional lossless realizing presurized water reactor spent fuel element detects, the invention 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 invention 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.Coaxial for guaranteeing two-dimensional detection imaging, present invention employs 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, have employed of the invention lays the method for 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 invention 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 invention 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, embodiments of the present invention are described further.
Embodiment
Adopt presurized water reactor spent fuel element of the present invention 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.
CN201510431174.8A 2015-07-21 2015-07-21 A kind of indirect neutron CT imaging devices of presurized water reactor spent fuel element Active CN105023622B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201510431174.8A CN105023622B (en) 2015-07-21 2015-07-21 A kind of indirect neutron CT imaging devices of presurized water reactor spent fuel element

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510431174.8A CN105023622B (en) 2015-07-21 2015-07-21 A kind of indirect neutron CT imaging devices of presurized water reactor spent fuel element

Publications (2)

Publication Number Publication Date
CN105023622A true CN105023622A (en) 2015-11-04
CN105023622B CN105023622B (en) 2018-01-19

Family

ID=54413523

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201510431174.8A Active CN105023622B (en) 2015-07-21 2015-07-21 A kind of indirect neutron CT imaging devices of presurized water reactor spent fuel element

Country Status (1)

Country Link
CN (1) CN105023622B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106872493A (en) * 2017-01-12 2017-06-20 中国原子能科学研究院 Nuclear fuel assembly nondestructive detection device
CN111063463A (en) * 2020-01-02 2020-04-24 中国原子能科学研究院 Carrying device and carrying method for nondestructive testing of fuel assembly
CN113916918A (en) * 2021-11-03 2022-01-11 中国原子能科学研究院 Detection system for neutron photography of radioactive samples

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02222886A (en) * 1989-02-14 1990-09-05 Toshiba Corp Measurement of concentration distribution of nuclear fuel substance and apparatus therefor
JP2006343284A (en) * 2005-06-10 2006-12-21 Global Nuclear Fuel-Japan Co Ltd Inspection device and inspection method of fuel assembly
CN102280149A (en) * 2011-06-28 2011-12-14 中国原子能科学研究院 Neutron photography detection device and detection method for nuclear fuel rod of pressurized water reactor
CN102324255A (en) * 2011-08-02 2012-01-18 中国核电工程有限公司 Thickness compensation method and compensation block for fuel rod end plug welding line X ray transillumination process
CN203688467U (en) * 2013-11-25 2014-07-02 中国核电工程有限公司 Nuclear rod end plug weld joint X-ray digital imaging and CT detection precision machinery device
CN204857197U (en) * 2015-07-21 2015-12-09 中国原子能科学研究院 Indirect neutron CT image device of weary fuel element of PWR

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02222886A (en) * 1989-02-14 1990-09-05 Toshiba Corp Measurement of concentration distribution of nuclear fuel substance and apparatus therefor
JP2006343284A (en) * 2005-06-10 2006-12-21 Global Nuclear Fuel-Japan Co Ltd Inspection device and inspection method of fuel assembly
CN102280149A (en) * 2011-06-28 2011-12-14 中国原子能科学研究院 Neutron photography detection device and detection method for nuclear fuel rod of pressurized water reactor
CN102324255A (en) * 2011-08-02 2012-01-18 中国核电工程有限公司 Thickness compensation method and compensation block for fuel rod end plug welding line X ray transillumination process
CN203688467U (en) * 2013-11-25 2014-07-02 中国核电工程有限公司 Nuclear rod end plug weld joint X-ray digital imaging and CT detection precision machinery device
CN204857197U (en) * 2015-07-21 2015-12-09 中国原子能科学研究院 Indirect neutron CT image device of weary fuel element of PWR

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
E.H.LEHMANN: "Non-destructive analysis of nuclear fuel by means of thermal and cold neutrons", 《NUCLEAR INSTRUMENTS AND METHODS IN PHYSICS RESEARCH》 *

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106872493A (en) * 2017-01-12 2017-06-20 中国原子能科学研究院 Nuclear fuel assembly nondestructive detection device
CN106872493B (en) * 2017-01-12 2019-09-13 中国原子能科学研究院 Nuclear fuel assembly nondestructive detection device
CN111063463A (en) * 2020-01-02 2020-04-24 中国原子能科学研究院 Carrying device and carrying method for nondestructive testing of fuel assembly
CN111063463B (en) * 2020-01-02 2024-05-31 中国原子能科学研究院 Object carrying device and object carrying method for nondestructive testing of fuel assembly
CN113916918A (en) * 2021-11-03 2022-01-11 中国原子能科学研究院 Detection system for neutron photography of radioactive samples

Also Published As

Publication number Publication date
CN105023622B (en) 2018-01-19

Similar Documents

Publication Publication Date Title
KR101179540B1 (en) Method for analyzing the Internal Density of Material using a X-ray Computerized Tomography
CN105023622A (en) Pressurized water reactor spent fuel element indirect neutron CT imaging device
CN105911077A (en) Test method for XCT nondestructive detection of sulfate erosion damages of concrete material
CN108271412B (en) Image acquisition device, image acquisition method, and image correction program
CN104359763A (en) Method for detecting internal crack developing of cement-based material under action of load
CN204857197U (en) Indirect neutron CT image device of weary fuel element of PWR
CN105161147A (en) Nondestructive testing method for spent fuel component of pressurized water reactor by virtue of three-dimensional neutron radiography
CN110286136B (en) X-ray three-dimensional imaging method and system for basin-type insulator of in-service GIS (gas insulated switchgear) combined electrical apparatus
CN104502379A (en) Method for testing corrosion of reinforcing steel bar inside concrete sample
West et al. Improved visual inspection of advanced gas-cooled reactor fuel channels
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
CN108760776B (en) Visual test method and system for water transmission in cement-based material
CN210894172U (en) X-ray small-angle scattering imaging system
JP2010185888A (en) Radiation nondestructive inspection system and piping inspection method
CN204086173U (en) A kind of fuel rod end plug weld seam detection plumbous cover of shielding
DE102012215120A1 (en) Evaluation device for testing electrochemical cell assembly, has data interface for receiving two sets of measurement data, which are determined for electrochemical cell assembly by two independent testing devices of set of testing devices
JP7051847B2 (en) X-ray in-line inspection method and equipment
Schrapp et al. Artifact reduction in industrial computed tomography via data fusion
Tigkos et al. Simulation study for optimization of X-ray inspection setup applied to CFRP aerostructures
CN118150616B (en) Ray detection simulation method based on digital twinning
CN114742771B (en) Automatic nondestructive measurement method for size of back drilling hole of circuit board
CN110111309A (en) Carbon fiber composite core wire ray image processing method, defect inspection method, device, equipment and computer storage medium
Feiste et al. Three dimensional analysis of growing casting effects

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant