CN112130194B - Neutron detector rapid inspection device - Google Patents

Neutron detector rapid inspection device Download PDF

Info

Publication number
CN112130194B
CN112130194B CN202010843590.XA CN202010843590A CN112130194B CN 112130194 B CN112130194 B CN 112130194B CN 202010843590 A CN202010843590 A CN 202010843590A CN 112130194 B CN112130194 B CN 112130194B
Authority
CN
China
Prior art keywords
neutron
shielding container
detection device
neutron source
neutron detector
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.)
Active
Application number
CN202010843590.XA
Other languages
Chinese (zh)
Other versions
CN112130194A (en
Inventor
刘国荣
梁庆雷
李井怀
鹿捷
马长江
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 CN202010843590.XA priority Critical patent/CN112130194B/en
Publication of CN112130194A publication Critical patent/CN112130194A/en
Application granted granted Critical
Publication of CN112130194B publication Critical patent/CN112130194B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00Details of radiation-measuring instruments
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • 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

  • 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 aftertreatment, and particularly relates to a rapid neutron detector inspection device which is used for measuring neutron detectors (10) in a serial detection device, wherein the serial detection device is formed by connecting a plurality of neutron detectors (10) in series, and is characterized in that: the device comprises a shielding container (4) with a neutron source (9) inside, wherein the shielding container (4) is also provided with a perforation (6) which can pass through the serial detection device. The rapid neutron detector inspection device provided by the invention has the advantages of small size, light weight and portability, realizes rapid inspection of each neutron detector (10) in the serial detection device without disassembling the serial detection device, and has simple and convenient inspection operation.

Description

Neutron detector rapid inspection device
Technical Field
The invention belongs to the technical field of spent fuel aftertreatment, and particularly relates to a neutron detector rapid inspection device.
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 of a nuclear power plant. 3% -4% of the uranium waste (spent fuel) that has been used is chemically separated from the fission products, known as spent fuel redissolution and post-processing techniques. Recycled uranium and plutonium can be recycled in mixed oxide fuels in nuclear power plants to produce more energy, thereby making more efficient use of uranium resources and reducing enrichment requirements. Post-treatment also aids in the final disposal of the waste by reducing the volume of high level waste and removing plutonium.
Solvent extraction equipment with good results commonly used in post-treatment plants are mixer-settler and pulsed extraction columns. The concentration of plutonium solution in the pulsed extraction column is one of the key objects of interest, directly reflecting the operating process conditions of the post-treatment plant. As shown in fig. 1, the current method for monitoring the concentration of plutonium solution in a pulse extraction column mainly comprises the steps of placing a serial detection device in a device room, wherein the serial detection device is formed by serially connecting a plurality of neutron detectors, the serial detection device is placed in a sleeve, and the serial detection device can enter and exit from the sleeve. The neutron detector in the serial detection device needs to be checked regularly, and how to check the serial detection device conveniently and quickly is one of important 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 serial detection device, so that the measurement result of the neutron detector is more accurate.
In order to achieve the above purpose, the technical scheme adopted by the invention is that the rapid neutron detector inspection device is used for measuring neutron detectors in a serial detection device, the serial detection device consists of a plurality of neutron detectors which are connected in series, wherein the rapid neutron detector inspection device comprises a shielding container with a neutron source inside, and the shielding container is also provided with a perforation which can pass through the serial 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 perforations extend through the shielded container.
Further, the neutron source is proximate to the perforation.
Further, the neutron source placing hole is plugged through a sealing plug.
Further, the shielding container is made of polyethylene, so that neutrons emitted by the neutron source can be slowed down.
Further, the sealing plug is made of polyethylene.
Further, the shielding container is a cylinder, the neutron source placement hole is located at the axis position of the shielding container, and the perforation passes through the vicinity of the sealed bottom end of the neutron source placement hole.
Further, 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 phi 250mm multiplied by 250mm, and the weight is about 12kg, so that the shielding container is convenient to carry.
2. A quick inspection of each neutron detector 10 in the tandem detector is achieved without the need to disassemble the tandem detector.
3. The inspection operation is simple and convenient.
Drawings
FIG. 1 is a schematic view of a sleeve 2 disposed on a pulsed extraction column 1 within an equipment room according to the background of the invention, a serial detection device consisting of several neutron detectors 10 connected in series being disposed within the sleeve 2;
FIG. 2 is a schematic perspective view of a neutron detector rapid inspection device according to an embodiment of the present invention;
FIG. 3 is a schematic plan view of a neutron detector rapid inspection device according to an embodiment of the present invention;
FIG. 4 is a view in the A direction of FIG. 3;
FIG. 5 is a view in the B direction of FIG. 3;
FIG. 6 is a schematic illustration of the detection process in a neutron detector rapid verification device described in the embodiments of the invention;
in the figure: 1-pulse extraction column, 2-sleeve, 3-wall, 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 drawings and examples.
As shown in fig. 2 to 5, the rapid neutron detector inspection device provided by the invention is used for measuring neutron detectors 10 in a serial detection device, the serial detection device is formed by connecting a plurality of neutron detectors 10 in series, the rapid neutron detector inspection device is a shielding container 4 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 also provided with a through hole 6 through which the serial detection device can pass.
The shielding container 4 is internally provided with a neutron source placing hole 8, and a neutron source 9 is arranged in the neutron source placing hole 8.
Perforations 6 extend through the shielded container 4.
The neutron source 9 is close to the perforation 6.
The neutron source placing hole 8 is blocked by the sealing plug 5.
The shielding container 4 is made of polyethylene, and can slow down neutrons emitted from the neutron source 9.
The sealing plug 5 is rod-shaped and made of polyethylene.
The shielding container 4 is a cylinder, the neutron source placement hole 8 is located at the axial position of the shielding container 4, and the perforation 6 passes through the vicinity of the sealed bottom end of the neutron source placement hole 8.
The shielding container 4 is also provided with a handle 7, so that an operator can conveniently carry the device to a designated position for operation.
The practical application of the neutron detector rapid inspection device 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, 9 neutron detectors 10 are required to be placed every 1 meter in the design plate section part, the neutron detectors 10 form a serial detection device to be placed in the sleeve 2, and the serial detectors can enter and exit the sleeve 2 by manpower.
As shown in fig. 6, a neutron source 9 is disposed in a neutron source placing hole 8 of a shielding container 4, and neutron detectors 10 on the serial detection device sequentially pass through perforations 6 to be inspected, and after one neutron detector 10 is inspected, the serial detection device is moved to test the next neutron detector 10 until all neutron detectors 10 are inspected.
All the connecting harnesses of the neutron detectors 10 are led out on one side of the serial detection device. During the inspection, the connecting wire harness is required to be connected to the corresponding electronic device for testing, if the neutron detector 10 fails and can be replaced in time, after the inspection is completed, the neutron source 9 is taken out, and the serial detection device is put into the sleeve 2 for continuous operation.
The device according to the invention is not limited to the examples described in the specific embodiments, and a person skilled in the art obtains other embodiments according to the technical solution of the invention, which also belong to the technical innovation scope of the invention.

Claims (4)

1. The utility model provides a neutron detector rapid inspection device for measure neutron detector (10) among the tandem detection device, the tandem detection device by a plurality of neutron detector (10) establish ties and constitute, characterized by: the device comprises a shielding container (4) with a neutron source (9) inside, wherein the shielding container (4) is also provided with a perforation (6) which can pass through the serial detection device;
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);
the perforations (6) extend through the shielding container (4);
-said neutron source (9) being close to said perforation (6);
the neutron source placing hole (8) is plugged by a sealing plug (5);
the shielding container (4) is made of polyethylene, and neutrons emitted by the neutron source (9) can be slowed down; the size of the shielding container (4) is phi 250mm multiplied by 250mm, the weight is 12kg, and the shielding container is convenient to carry.
2. The rapid neutron detector inspection device of claim 1, wherein: the sealing plug (5) is made of polyethylene.
3. The rapid neutron detector inspection device of claim 1, wherein: the shielding container (4) is a cylinder, the neutron source placing hole (8) is positioned at the axis position of the shielding container (4), and the perforation (6) passes through the vicinity of the sealed bottom end of the neutron source placing hole (8).
4. The rapid neutron detector inspection device of claim 1, wherein: and a handle (7) is also arranged on the shielding container (4).
CN202010843590.XA 2020-08-20 2020-08-20 Neutron detector rapid inspection device Active CN112130194B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202010843590.XA CN112130194B (en) 2020-08-20 2020-08-20 Neutron detector rapid inspection device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202010843590.XA CN112130194B (en) 2020-08-20 2020-08-20 Neutron detector rapid inspection device

Publications (2)

Publication Number Publication Date
CN112130194A CN112130194A (en) 2020-12-25
CN112130194B true CN112130194B (en) 2024-02-20

Family

ID=73851660

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202010843590.XA Active CN112130194B (en) 2020-08-20 2020-08-20 Neutron detector rapid inspection device

Country Status (1)

Country Link
CN (1) CN112130194B (en)

Citations (8)

* Cited by examiner, † Cited by third party
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
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
CN108007948A (en) * 2017-12-22 2018-05-08 安徽海螺集团有限责任公司 Neutron activation analysis equipment
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

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20120166128A1 (en) * 2010-12-28 2012-06-28 Ikhlef Abdelaziz Method and apparatus for detector calibration

Patent Citations (8)

* Cited by examiner, † Cited by third party
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
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

Also Published As

Publication number Publication date
CN112130194A (en) 2020-12-25

Similar Documents

Publication Publication Date Title
CN107796668A (en) A kind of nuclear power plant's spent resin processing method
CN112130194B (en) Neutron detector rapid inspection device
CN109100772A (en) A kind of on-line analysis monitoring method and device for spentnuclear fuel course of dissolution
CN111638540A (en) Device, method, equipment and storage medium for measuring radioactive inert gas
Lafleur et al. Development of self-interrogation neutron resonance Densitometry to improve detection of possible diversions for PWR spent fuel assemblies
Mihalczo et al. 252 Cf-source-driven neutron noise analysis method
Mauerhofer et al. Quantitative comparison between PGNAA measurements and MCNP calculations in view of the characterization of radioactive wastes in Germany and France
Murphy et al. Neutronics investigations for the lower part of a Westinghouse SVEA-96+ assembly
KR100332712B1 (en) Measuring method for fissile content in nuclear fuel material using cadmium ratio of neutron counts and its equipment
KR102607743B1 (en) Monitoring methods for neutron fluence of reactor pressure vessel
Cobb et al. Nondestructive verification and assay systems for spent fuels. Technical appendixes
CN112147163B (en) A series detection device for multiple spot measurement pulse extraction post plutonium concentration
Chichester et al. Neutron resonance transmission analysis (NRTA): initial studies of a method for assaying plutonium in spent fuel
Lienkov et al. The Development of an Intelligent Complex of Radiation-Technological Control of a Safety Barrier
Fougeras et al. MISTRAL-4: an experimental mockup in the EOLE facility devoted to high moderation 100% MOX core Physics
Chichester et al. Active interrogation using electronic neutron generators for nuclear safeguards applications
Rataj et al. Application of the Source-Jerk method using a neutron generator in a subcritical reactor
Leconte et al. Reactivity loss validation of high-burnup PWR fuels with pile-oscillation experiments in MINERVE
Rypar et al. Determination of power density in VVER-1000 Mock-Up in LR-0 reactor
Rao et al. Verification of Shielding Calculation Capability of RMC With HB Robinson-2 Pressure Vessel Benchmark
East et al. Fundamental fission signatures and their applications to nuclear safeguards
Grape et al. Partial defect evaluation methodology for nuclear safeguards inspections of used nuclear fuel using the digital Cherenkov viewing device
Oleinik et al. Determination of the burnup of spent nuclear fuel during reloading
Chen Vanadium Self-Powered Detector Gamma Response in Commercial Pressurized Water Reactor
Trahan Safeguarding Reactors and Spent Nuclear Fuel [Slides]

Legal Events

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