CN112130194A - Quick verifying attachment of neutron detector - Google Patents
Quick verifying attachment of neutron detector Download PDFInfo
- Publication number
- CN112130194A CN112130194A CN202010843590.XA CN202010843590A CN112130194A CN 112130194 A CN112130194 A CN 112130194A CN 202010843590 A CN202010843590 A CN 202010843590A CN 112130194 A CN112130194 A CN 112130194A
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- Prior art keywords
- neutron
- neutron detector
- detection device
- shielding container
- neutron source
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- 238000001514 detection method Methods 0.000 claims abstract description 34
- 238000007689 inspection Methods 0.000 claims abstract description 22
- 238000007789 sealing Methods 0.000 claims description 7
- 239000004698 Polyethylene Substances 0.000 claims description 6
- -1 polyethylene Polymers 0.000 claims description 6
- 229920000573 polyethylene Polymers 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 6
- 238000012360 testing method Methods 0.000 abstract description 4
- 238000012805 post-processing Methods 0.000 abstract description 3
- 238000000605 extraction Methods 0.000 description 7
- 238000000034 method Methods 0.000 description 6
- 229910052778 Plutonium Inorganic materials 0.000 description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 5
- 229910052770 Uranium Inorganic materials 0.000 description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 4
- 238000005259 measurement Methods 0.000 description 2
- 230000035515 penetration Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
Images
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
-
- 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
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- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention belongs to the technical field of spent fuel post-processing, and particularly relates to a fast testing device for a neutron detector, which is used for measuring the neutron detector (10) in a series detection device, wherein the series detection device is formed by connecting a plurality of neutron detectors (10) in series, and is characterized in that: the neutron source detection device comprises a shielding container (4) with an internal neutron source (9), wherein a through hole (6) capable of passing through the series detection device is further formed in the shielding container (4). The neutron detector rapid inspection device provided by the invention is small in size, light in weight and convenient to carry, can realize rapid inspection of each neutron detector (10) in the series detection device without disassembling the series detection device, and is simple and convenient in inspection operation.
Description
Technical Field
The invention belongs to the technical field of spent fuel post-processing, and particularly relates to a fast testing device for a neutron detector.
Background
Spent fuel, also known as irradiated nuclear fuel, is spent nuclear fuel that has been subjected to irradiation, typically produced by a nuclear reactor in a nuclear power plant. From 3% to 4% of the uranium waste (spent fuel) that has been used, uranium and plutonium are chemically separated from the fission products, a technique known as spent fuel redissolution and reprocessing. The recovered uranium and plutonium can be recycled in the mixed oxide fuel of the nuclear power plant to produce more energy, thereby enabling the uranium resources to be more fully utilized and reducing the concentration requirements. Post-processing also aids in the final disposal of the waste by reducing the volume of the high level waste and removing plutonium.
The commonly used solvent extraction equipment with good effect in the post-treatment plant is a mixer-settler and a pulse extraction column. The concentration of the plutonium solution in the pulse extraction column is one of the key objects of concern, and directly reflects the operating process state of the post-treatment plant. As shown in fig. 1, in the current method for monitoring the concentration of plutonium solution in a pulse extraction column, a series detection device is mainly placed in an equipment room close to the pulse extraction column for measurement, the series detection device is formed by connecting a plurality of neutron detectors in series and is placed in a sleeve, and the series detection device can enter and exit from the sleeve. The neutron detector in the series detection device needs to be checked regularly, and how to conveniently and quickly check the series detection device is one of the key points of research.
Disclosure of Invention
The invention aims to provide a detection device which can be used for rapidly detecting each neutron detector in a series detection device, so that the measurement result of the neutron detectors is more accurate.
In order to achieve the above purpose, the invention adopts the technical scheme that the neutron detector rapid inspection device is used for measuring neutron detectors in a series detection device, the series detection device is formed by connecting a plurality of neutron detectors in series, the neutron detector rapid inspection device comprises a shielding container internally provided with a neutron source, and the shielding container is also provided with a through hole capable of passing through the series detection device.
Further, a neutron source placing hole is formed in the shielding container, and the neutron source is arranged in the neutron source placing hole.
Further, the perforation penetrates through the shielding container.
Further, the neutron source is proximate to the perforation.
Further, the neutron source placing hole is sealed and sealed through a sealing plug.
Furthermore, the shielding container is made of polyethylene, and neutrons emitted by the neutron source can be moderated.
Further, the material of the sealing plug is polyethylene.
Further, the shielding container is a cylindrical body, the neutron source placement hole is located at an axial position of the shielding container, and the penetration hole penetrates from the vicinity of a sealed bottom end of the neutron source placement hole.
Furthermore, a handle is further arranged on the shielding container.
The invention has the beneficial effects that:
1. the size of the shielding container 4 is about 250mm x 250mm, and the weight is about 12kg, which is convenient for carrying.
2. The rapid inspection of each neutron detector 10 in the series detection arrangement is achieved without disassembling the series detection arrangement.
3. The inspection operation is simple and convenient.
Drawings
Fig. 1 is a schematic view of a casing 2 disposed on a pulse extraction column 1 in an equipment room according to the background of the present invention, and a serial detection device composed of a plurality of neutron detectors 10 connected in series is disposed in the casing 2;
FIG. 2 is a schematic perspective view of a neutron detector rapid inspection device according to an embodiment of the invention;
FIG. 3 is a schematic plan view of a neutron detector rapid inspection device according to an embodiment of the invention;
FIG. 4 is a view in the direction A of FIG. 3;
FIG. 5 is a view from the direction B of FIG. 3;
FIG. 6 is a schematic diagram of a detection process of a serial detection device in a fast neutron detector inspection device according to an embodiment of the invention;
in the figure: the method comprises the following steps of 1-pulse extraction column, 2-casing pipe, 3-wall body, 4-shielding container, 5-sealing plug, 6-perforation, 7-handle, 8-neutron source placing hole, 9-neutron source and 10-neutron detector.
Detailed Description
The invention is further described below with reference to the figures and examples.
As shown in fig. 2 to 5, the fast neutron detector inspection device provided by the present invention is used for measuring a neutron detector 10 in a series detection device, the series detection device is formed by connecting a plurality of neutron detectors 10 in series, the fast neutron detector inspection device provided by the present invention is a shielding container 4 provided with a neutron source 9 inside, the shielding container 4 can shield radioactive particles emitted by the neutron source 9, and the shielding container 4 is further provided with a through hole 6 capable of passing through the series detection device.
A neutron source placing hole 8 is formed in the shielding container 4, and a neutron source 9 is arranged in the neutron source placing hole 8.
A perforation 6 penetrates the shielding container 4.
A neutron source 9 is adjacent the perforation 6.
The neutron source placement hole 8 is closed by a sealing plug 5.
The material of the shield container 4 is polyethylene, and neutrons emitted from the neutron source 9 can be moderated.
The sealing plug 5 is rod-shaped and made of polyethylene.
The shielding container 4 is a cylindrical body, the neutron source placement hole 8 is located at the axial position of the shielding container 4, and the penetration hole 6 penetrates from the vicinity of the sealed bottom end of the neutron source placement hole 8.
The shielding container 4 is also provided with a lifting handle 7, so that an operator can conveniently lift the device to a designated position for operation.
The practical application of the fast testing device for the neutron detector provided by the invention is illustrated;
as shown in fig. 1, the height of the pulse extraction column 1 is about 12.3 meters, the height of the plate section part is about 8 meters, and the plate section part is designed to be provided with one neutron detector 10 every 1 meter, so that 9 neutron detectors 10 are required in total, the neutron detectors 10 form a series detection device and are placed in the casing 2, and the series detectors can enter and exit the casing 2 through manpower.
The process of inspecting the series detection device is shown in fig. 6, a neutron source 9 is arranged in a neutron source placing hole 8 of the shielding container 4, the neutron detectors 10 on the series detection device are sequentially inspected through the through holes 6, after one neutron detector 10 is inspected, the series detection device is moved, and the next neutron detector 10 is tested until all the neutron detectors 10 are inspected.
The connecting wire bundles of all the neutron detectors 10 are led out from one side of the series detection device. During inspection, the connecting wire harness is required to be connected to a corresponding electronic device for testing, if the neutron detector 10 fails, the neutron detector can be replaced in time, after the inspection is finished, the neutron source 9 is taken out, and the series detection device is placed in the sleeve 2 for continuous work.
The device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (9)
1. The utility model provides a quick verifying attachment of neutron detector for measure neutron detector (10) among the detection device of establishing ties, the detection device of establishing ties is by a plurality of neutron detector (10) are established ties and are constituteed, characterized by: the neutron source detection device comprises a shielding container (4) with an internal neutron source (9), wherein a through hole (6) capable of passing through the series detection device is further formed in the shielding container (4).
2. The fast neutron detector inspection device of claim 1, wherein: a neutron source placing hole (8) is formed in the shielding container (4), and the neutron source (9) is arranged in the neutron source placing hole (8).
3. The neutron detector rapid inspection device of claim 2, wherein: the perforation (6) penetrates the shielding container (4).
4. The neutron detector rapid inspection device of claim 3, wherein: the neutron source (9) is adjacent to the perforation (6).
5. The neutron detector rapid inspection device of claim 4, wherein: the neutron source placing hole (8) is plugged by a sealing plug (5).
6. The fast neutron detector inspection device of claim 1, wherein: the shielding container (4) is made of polyethylene, and neutrons emitted by the neutron source (9) can be moderated.
7. The neutron detector rapid inspection device of claim 5, wherein: the material of the sealing plug (5) is polyethylene.
8. The neutron detector rapid inspection device of claim 4, wherein: the shielding container (4) is a cylinder, the neutron source placing hole (8) is located at the axial position of the shielding container (4), and the through hole (6) penetrates through the vicinity of the sealed bottom end of the neutron source placing hole (8).
9. The fast neutron detector inspection device of claim 1, wherein: and a handle (7) is also arranged on the shielding container (4).
Priority Applications (1)
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CN202010843590.XA CN112130194B (en) | 2020-08-20 | 2020-08-20 | Neutron detector rapid inspection device |
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CN202010843590.XA CN112130194B (en) | 2020-08-20 | 2020-08-20 | Neutron detector rapid inspection device |
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CN112130194A true CN112130194A (en) | 2020-12-25 |
CN112130194B CN112130194B (en) | 2024-02-20 |
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113885071A (en) * | 2021-09-02 | 2022-01-04 | 中广核工程有限公司 | Method for verifying validity of reactor core subcritical supervision neutron detector |
Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN201359637Y (en) * | 2009-03-04 | 2009-12-09 | 中国核电工程有限公司 | Shielding tungsten block of passive detector |
US20120166128A1 (en) * | 2010-12-28 | 2012-06-28 | Ikhlef Abdelaziz | Method and apparatus for detector calibration |
CN203867565U (en) * | 2014-04-16 | 2014-10-08 | 鞍山申阔机械制造有限公司 | While-drilling neutron logger device |
CN104464853A (en) * | 2014-11-27 | 2015-03-25 | 中国船舶重工集团公司第七一九研究所 | On-line boron concentration monitoring device |
CN108007948A (en) * | 2017-12-22 | 2018-05-08 | 安徽海螺集团有限责任公司 | Neutron activation analysis equipment |
CN108008442A (en) * | 2015-06-04 | 2018-05-08 | 东芝医疗系统株式会社 | Experimental rig and test method |
CN207396751U (en) * | 2017-08-31 | 2018-05-22 | 成都新核泰科科技有限公司 | A kind of Low background shields vitriol chamber |
CN208026877U (en) * | 2018-02-01 | 2018-10-30 | 西安电子科技大学 | A kind of neutron detector Performance Test System |
CN109212587A (en) * | 2018-08-10 | 2019-01-15 | 苏州速核仪器有限公司 | The measuring device of automatic amendment scintillation detector radiation detection efficiency |
-
2020
- 2020-08-20 CN CN202010843590.XA patent/CN112130194B/en active Active
Patent Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN201359637Y (en) * | 2009-03-04 | 2009-12-09 | 中国核电工程有限公司 | Shielding tungsten block of passive detector |
US20120166128A1 (en) * | 2010-12-28 | 2012-06-28 | Ikhlef Abdelaziz | Method and apparatus for detector calibration |
CN203867565U (en) * | 2014-04-16 | 2014-10-08 | 鞍山申阔机械制造有限公司 | While-drilling neutron logger device |
CN104464853A (en) * | 2014-11-27 | 2015-03-25 | 中国船舶重工集团公司第七一九研究所 | On-line boron concentration monitoring device |
CN108008442A (en) * | 2015-06-04 | 2018-05-08 | 东芝医疗系统株式会社 | Experimental rig and test method |
CN207396751U (en) * | 2017-08-31 | 2018-05-22 | 成都新核泰科科技有限公司 | A kind of Low background shields vitriol chamber |
CN108007948A (en) * | 2017-12-22 | 2018-05-08 | 安徽海螺集团有限责任公司 | Neutron activation analysis equipment |
CN208026877U (en) * | 2018-02-01 | 2018-10-30 | 西安电子科技大学 | A kind of neutron detector Performance Test System |
CN109212587A (en) * | 2018-08-10 | 2019-01-15 | 苏州速核仪器有限公司 | The measuring device of automatic amendment scintillation detector radiation detection efficiency |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113885071A (en) * | 2021-09-02 | 2022-01-04 | 中广核工程有限公司 | Method for verifying validity of reactor core subcritical supervision neutron detector |
CN113885071B (en) * | 2021-09-02 | 2024-07-19 | 中广核工程有限公司 | Method for verifying effectiveness of reactor core subcritical supervision neutron detector |
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