CN117969558A - Quick testing arrangement of thermal neutron protective material performance - Google Patents
Quick testing arrangement of thermal neutron protective material performance Download PDFInfo
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- CN117969558A CN117969558A CN202311624026.9A CN202311624026A CN117969558A CN 117969558 A CN117969558 A CN 117969558A CN 202311624026 A CN202311624026 A CN 202311624026A CN 117969558 A CN117969558 A CN 117969558A
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- 238000012360 testing method Methods 0.000 title claims abstract description 73
- 239000000463 material Substances 0.000 title claims abstract description 44
- 230000001681 protective effect Effects 0.000 title claims abstract description 18
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 17
- 229910002804 graphite Inorganic materials 0.000 claims description 16
- 239000010439 graphite Substances 0.000 claims description 16
- 229910000838 Al alloy Inorganic materials 0.000 claims description 11
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 11
- 229910052796 boron Inorganic materials 0.000 claims description 11
- 239000004698 Polyethylene Substances 0.000 claims description 10
- -1 polyethylene Polymers 0.000 claims description 10
- 229920000573 polyethylene Polymers 0.000 claims description 10
- 229910052793 cadmium Inorganic materials 0.000 claims description 8
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims description 8
- 230000000694 effects Effects 0.000 claims description 5
- 229910052580 B4C Inorganic materials 0.000 claims description 3
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 3
- 238000012545 processing Methods 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- 229910052790 beryllium Inorganic materials 0.000 claims description 2
- 230000001105 regulatory effect Effects 0.000 abstract 1
- 238000000034 method Methods 0.000 description 6
- 230000005855 radiation Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- 238000001228 spectrum Methods 0.000 description 3
- 229910000978 Pb alloy Inorganic materials 0.000 description 2
- 230000007613 environmental effect Effects 0.000 description 2
- 238000011156 evaluation Methods 0.000 description 2
- 238000005457 optimization Methods 0.000 description 2
- 206010028980 Neoplasm Diseases 0.000 description 1
- 201000011510 cancer Diseases 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000000921 elemental analysis Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000001956 neutron scattering Methods 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 238000004154 testing of material Methods 0.000 description 1
- 238000002366 time-of-flight method Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/005—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by using neutrons
-
- 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)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Measurement Of Radiation (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
Abstract
The invention discloses a thermal neutron protective material performance rapid testing device, which comprises: the device comprises a thermal neutron source device, an adjusting rail, a sample adjusting frame, a counter shield and an equipment terminal. The thermal neutron source device is used for acquiring thermal neutrons required by the test; the adjusting rail is used for placing the sample adjusting frame and the counter and adjusting the position between the sample adjusting frame and the thermal neutron outlet; the counter is connected with the regulating track through a bus and is used for receiving neutrons entering the counter; the counter shield is used to shield neutrons scattered by the surrounding environment. The device provided by the invention can be used for conveniently, effectively and rapidly testing the shielding performance of shielding materials and protective clothing with any size.
Description
Technical Field
The invention relates to a neutron performance rapid testing device, in particular to a thermal neutron protective material performance rapid testing device.
Technical Field
Neutrons were found by the uk physicist chadwik in 1932. Through development for 90 years, the understanding of neutrons by scientific researchers has been significantly improved, and neutrons are also applied in various fields, such as neutron imaging, boron neutron capture methods for cancer treatment, explosion detection, elemental analysis and the like. Although neutrons provide great benefits to humans, excessive neutron irradiation is very dangerous to the human body. In the design of nuclear radiation, the radiation protection optimization "ALARA" principle is widely accepted in order to protect humans from a safe working environment. The following three principles are required to meet the radiation protection optimization requirements: firstly, a time protection principle is adopted to reduce exposure time as much as possible; secondly, the distance protection principle is that the distance between the radiator and a person is increased as much as possible; thirdly, selecting an optimal shielding protection principle.
For shielding protection, a shielding protection material with the best performance is selected as a protection means. Therefore, the novel shielding material is always a research hot spot in the field of radiation protection. For a new shielding material, the first thing is to make a test evaluation of its shielding performance. There are various methods for evaluating neutron shielding performance. The most accurate method in theory is to measure neutron energy spectrum, the shielding performance of shielding materials is obtained by comparing neutron energy spectrum, and the common methods for measuring neutron energy spectrum are a time-of-flight method and a buna multi-sphere neutron spectrometer, but the testing process is more complex and the testing efficiency is low. The most common method at present is to measure its dose equivalent rate by neutron dosimeters and evaluate the shielding material performance by comparing the ambient dose equivalent rate with or without shielding material. But for thermal neutrons or relatively thin shielding materials neutron dosimeters will no longer be suitable.
The conventional neutron shielding material testing device is mainly based on performance evaluation of a fast neutron shielding material, and neutrons protected by protective clothing or a thinner shielding material are mainly thermal neutrons or epithermal neutrons; in addition, the position of the test sample needs to be frequently adjusted when the uniformity index of the protective material is measured, and the test time for the test sample with larger test size is longer.
Disclosure of Invention
Aiming at the defects existing in the prior art, the invention aims to provide a device for rapidly testing the performance of a thermal neutron protective material, which can more conveniently, more effectively and rapidly test the shielding performance of shielding materials and protective clothing with any size.
In order to meet the above requirements, the invention provides a device for rapidly testing the performance of a thermal neutron protective material, which comprises: the neutron source, the shielding and slowing device arranged outside the neutron source, the neutron source switch arranged outside the shielding and slowing device, the test sample adjusting rack, the counter shielding body, the counter, the adjusting rail and the equipment terminal; the neutron source and the shielding and slowing device form a thermal neutron device together and are used for acquiring thermal neutrons; the test sample adjusting frame is arranged on the adjusting track and is mainly used for placing a test sample; the counter shield is to shield neutrons scattered by the surrounding environment; the adjusting track is used for adjusting the positions of the test sample and the counter; the equipment terminal is used for controlling the adjusting track, the neutron source switch and processing data obtained by the counter.
Further, the slowing device is composed of an aluminum alloy shell, lead, boron-containing polyethylene and graphite from outside to inside in sequence.
Further, the thickness of the aluminum alloy shell in the shielding and slowing device is 3-5mm.
Further, the thickness of the lead layer in the shielding and slowing device is 20cm-30cm in the horizontal direction and the vertical direction.
Further, the mass fraction of boron carbide contained in the boron-containing polyethylene layer in the shielding and slowing device is 10% -20%, and the thicknesses in the horizontal direction and the vertical direction are 7cm-15cm.
Further, the thickness of the graphite layer in the shielding and slowing device in the horizontal direction is more than or equal to 100cm, and the thickness in the vertical direction is more than or equal to 75cm.
Further, the horizontal outlet of the shielding and slowing device is in a strip shape.
Further, the neutron source is americium-beryllium neutron source, is positioned on the left of the center of the graphite of the moderated body, is wrapped by a steel ladle with phi of 2.42cm multiplied by 3cm, has activity of 10 11～1015 Bq, and is mainly thermal neutrons emitted after the graphite moderation.
Further, the counter is an H-3 proportional counter.
Further, the neutron source switch is made of cadmium, and the thickness of the neutron source switch is 2mm-5mm;
the equipment terminal comprises a computer, a preamplifier and a NIM cabinet, wherein the preamplifier is connected with the NIM cabinet and the counter, and a thermal neutron source is used for switching on and off and an adjusting track is connected through a bus;
the sample adjusting frame is used for adjusting a plurality of dimensions in the front-back, left-right and the like.
The invention has the technical effects that the rapid testing device for the performance of the thermal neutron protective material can test a test sample more conveniently and effectively, and has the following advantages:
(1) The thermal neutron source selects the optimized slowing layer and shielding layer through analog measurement and experimental measurement, and the device is more economical and safer.
(2) The thermal neutron source is designed with the outgoing collimation channel, cadmium is wrapped around the counter, the environmental interference signals received by the counter are few, and the reliability of the test result is high.
(3) The sample adjusting frame can adjust the positions of two dimensions, and can rapidly and continuously measure different areas of a test material.
Drawings
FIG. 1 is a schematic diagram of a device for rapidly testing the performance of a thermal neutron shielding material in an embodiment of the invention.
Fig. 2 is a schematic diagram of the effective test area and counter count area of the device in an embodiment of the invention.
Detailed Description
The following description of the technical solutions in the embodiments of the present invention will be clear and complete, and it is obvious that the described embodiments are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
According to the rapid thermal neutron protective material performance testing device, graphite, boron-containing polyethylene, lead and aluminum alloy shells are added outside a neutron source to obtain quasi-parallel thermal neutron beams, and a test sample is placed on a sample adjusting frame, so that rapid measurement can be realized. Since neutron scattering has a large influence on the counter, a counter shield is manufactured, and the shield material is cadmium and is used for absorbing environmental scattered neutrons.
As shown in fig. 1, a device for rapidly testing the performance of a thermal neutron shielding material, the device comprising: the device comprises a neutron source switch 1, a neutron source 6, shielding and slowing-down devices 2-5 arranged on the outer side of the neutron source, a test sample adjusting frame 7, a counter shielding body 8, a counter 9, an adjusting rail 10 and an equipment terminal 11. The neutron source switch 1 is arranged on the outer side of the shielding and slowing-down device 5, and the neutron source 6 and the shielding and slowing-down devices 2-5 form a thermal neutron device together and are used for acquiring thermal neutrons; the test sample adjusting frame 7 is arranged on the adjusting rail 10 and is mainly used for placing a test sample; the counter 9 shield 8 is provided to shield neutrons scattered by the surrounding environment; the adjusting rail 10 is used for adjusting the positions of the test sample and the counter through the sample adjusting frame 7; the device terminal 11 is used for controlling the adjustment track 10, the neutron source switch 1 and processing the data obtained by the counter.
The effective test area is a neutron irradiation area which is the same as a thermal neutron exit on the test material in general size.
Wherein the counter counting area is a circular area with the diameter of 32mm, and the circular area is positioned in an area, opposite to the test sample, of the effective receiving area of the counter.
The thermal neutron source is an Am-Be neutron source, the thermal neutron source is positioned on the left side of the center of the graphite of the moderating body, the shielding moderating device consists of graphite, boron-containing polyethylene, lead and aluminum alloy shells, and an active switch is arranged at the outlet. The graphite is mainly used for moderating neutrons; the boron-containing polyethylene is used as a shielding body for shielding thermal neutrons; the lead is used for shielding gamma rays generated by neutrons; the source switch is used for controlling the on and off of the thermal neutron source device.
The equipment terminal comprises a computer, a preamplifier and a NIM cabinet, wherein the preamplifier is connected with the NIM cabinet and the counter. The thermal neutron source is switched on and the adjusting track is connected through a bus.
Wherein fig. 2 is a schematic view of an irradiation area and an effective test area of the device of the present invention, a represents the effective test area, its size is Φ=15mm, b represents the detector receiving area, and it is a circular area of Φ=32mm. In order to reduce the effect of ambient scattered neutrons on the counter as much as possible, it is required that the counter counting area is located at the centre of the active test area during the test.
Further, the Am-Be neutron source is wrapped by a steel ladle shell with phi of 2.42cm multiplied by 3cm, and the activity is 3.7 multiplied by 10 11 Bq.
Further, the thickness of the graphite layer in the shielding and slowing device in the horizontal direction is more than or equal to 100cm, and the thickness in the vertical direction is more than or equal to 75cm.
Further, the mass fraction of boron carbide contained in the boron-containing polyethylene in the shielding and slowing device is 10%, and the thicknesses in the horizontal direction and the vertical direction are 7cm.
Further, the thickness of the lead in the shielding and slowing device is 20cm in the horizontal direction and the vertical direction.
Further, the thickness of the aluminum alloy shell in the shielding and slowing device is 3-5mm.
Further, the neutron source switch is made of cadmium, and the thickness of the neutron source switch is 2mm.
Further, to ensure the validity of the test, the sheet sample must be greater than 20mm at the minimum test dimension.
Further, the counter is an H-3 proportional counter, the distance from the counter to the test sample is 2cm, and the detector is 12cm long.
In order to more specifically describe a device for rapidly testing the performance of a thermal neutron shielding material according to the present invention, a detailed description will be given below with reference to example 1.
Example 1
A thermal neutron protective material performance rapid test device is shown in fig. 1, and is a schematic diagram of the thermal neutron protective material performance rapid test device. The device comprises: the neutron source 6 is sequentially arranged on the graphite 5, the boron-containing polyethylene 4, the lead 3 and the aluminum alloy shell 2 outside the neutron source 6, the cadmium switch 1, the sample adjusting frame 7, the counter shielding body 8 and the counter 9 are arranged on the outer side of the aluminum alloy shell 2, the sample adjusting frame 7 is arranged on the adjusting track 10, and the equipment terminal 11 is arranged on the outer side of the aluminum alloy shell 2. In addition, the test device also comprises a valid test area and a counter counting area. The neutron source 6, the graphite 5, the boron-containing polyethylene 5, the lead 3, the aluminum alloy shell 2 and the cadmium switch 1 form a thermal neutron source device.
The sample adjusting frame 7 is used for placing a sample to be tested, and the position of the sample adjusting frame 7 can be adjusted by the equipment terminal so as to change the effective test area of the sample. The neutron source 6 emits fast neutrons, the fast neutrons are slowed down by the graphite 5 to generate thermal neutrons, the thermal neutrons pass through the long and narrow outlet channel to generate quasi-parallel thermal neutron beams, and neutrons and gamma rays in other directions at the outlet are shielded and absorbed. The thermal neutron beam is incident on the sample, and a post-sample counter records thermal neutrons passing through the sample and transmits counting information to a device terminal. The testing method comprises the following steps: counter count I 0 with no test material and open partition; detector count I 1 with test material; counting the detector I 2 when the isolating switch is in the off state; and under the closing state of the cadmium switch, placing the protective material on the sample adjusting frame for counting by the detector. The mask rate S is calculated according to the following formula parameters.
In conclusion, the device for rapidly testing the thermal neutron shielding material performance can test the thermal neutron shielding performance of the sheet shielding material and the protective clothing, can rapidly scan and test the material, has little influence on the test by the environment, and has high reliability of the test result.
While the present invention has been described in detail through the foregoing description of the preferred embodiment, it should be understood that the foregoing description is not to be considered as limiting the invention. Many modifications and substitutions of the present invention will become apparent to those of ordinary skill in the art upon reading the foregoing. Accordingly, the scope of the invention should be limited only by the attached claims.
Claims (10)
1. A thermal neutron protective material performance rapid test device is characterized in that the device comprises: a neutron source (6), a shielding and slowing device arranged outside the neutron source (6), a neutron source switch (1) arranged outside the shielding and slowing device, a test sample adjusting frame (7), a counter shielding body (8), a counter (9), an adjusting rail (10) and an equipment terminal (11); the neutron source (6) and the shielding and slowing device form a thermal neutron device together and are used for acquiring thermal neutrons; the test sample adjusting frame (7) is arranged on the adjusting rail (10) and is mainly used for placing a test sample; the counter shield (8) is provided to shield neutrons scattered by the surrounding environment; the adjusting track (10) is used for adjusting the positions of the test sample and the counter (9); the device terminal (11) is used for controlling the adjusting track (10), the neutron source switch (1) and processing data obtained by the counter.
2. The rapid thermal neutron protective material performance testing device according to claim 1, wherein the slowing device is composed of an aluminum alloy shell (2), lead (3), boron-containing polyethylene (4) and graphite (5) from outside to inside in sequence.
3. The rapid thermal neutron shielding material performance testing device according to claim 2, wherein the thickness of the aluminum alloy shell in the shielding and slowing device is 3-5mm.
4. The rapid thermal neutron shielding material performance testing device according to claim 2, wherein the thickness of the lead layer in the shielding and slowing device is 20cm-30cm in the horizontal direction and the vertical direction.
5. The rapid thermal neutron shielding material performance testing device according to claim 2, wherein the mass fraction of boron carbide contained in the boron-containing polyethylene layer in the shielding and slowing device is 10% -20%, and the thicknesses in the horizontal direction and the vertical direction are 7cm-15cm.
6. The rapid thermal neutron shielding material performance testing device according to claim 2, wherein the thickness of the graphite layer in the shielding and slowing device in the horizontal direction is more than or equal to 100cm, and the thickness in the vertical direction is more than or equal to 75cm.
7. The rapid thermal neutron shielding material performance testing device according to claim 2, wherein the horizontal outlet of the shielding and slowing device is in a strip shape.
8. The rapid thermal neutron shielding material performance testing device according to claim 1, wherein the neutron source is americium-beryllium neutron source, is positioned on the left of the center of graphite of the moderating body, is wrapped by a steel ladle with phi of 2.42cm multiplied by 3cm, has activity of 10 11～1015 Bq, and is mainly thermal neutrons emitted after the graphite moderation.
9. The rapid thermal neutron shielding material performance testing device according to claim 1, wherein the counter is an H-3 proportional counter.
10. The rapid thermal neutron shielding material performance testing device according to claim 1, wherein the neutron source switch is made of cadmium, and the thickness of the neutron source switch is 2mm-5mm;
the equipment terminal comprises a computer, a preamplifier and a NIM cabinet, wherein the preamplifier is connected with the NIM cabinet and the counter, and a thermal neutron source is used for switching on and off and an adjusting track is connected through a bus;
the sample adjusting frame is used for adjusting a plurality of dimensions in the front-back, left-right and the like.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311624026.9A CN117969558A (en) | 2023-11-30 | 2023-11-30 | Quick testing arrangement of thermal neutron protective material performance |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311624026.9A CN117969558A (en) | 2023-11-30 | 2023-11-30 | Quick testing arrangement of thermal neutron protective material performance |
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| Publication Number | Publication Date |
|---|---|
| CN117969558A true CN117969558A (en) | 2024-05-03 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311624026.9A Pending CN117969558A (en) | 2023-11-30 | 2023-11-30 | Quick testing arrangement of thermal neutron protective material performance |
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| Country | Link |
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| CN (1) | CN117969558A (en) |
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- 2023-11-30 CN CN202311624026.9A patent/CN117969558A/en active Pending
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