CN220085074U - Wide-energy-response neutron dose rate measuring instrument - Google Patents
Wide-energy-response neutron dose rate measuring instrument Download PDFInfo
- Publication number
- CN220085074U CN220085074U CN202321175656.8U CN202321175656U CN220085074U CN 220085074 U CN220085074 U CN 220085074U CN 202321175656 U CN202321175656 U CN 202321175656U CN 220085074 U CN220085074 U CN 220085074U
- Authority
- CN
- China
- Prior art keywords
- neutron
- layer
- polyethylene
- thickness
- dose rate
- 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
Links
- 239000004698 Polyethylene Substances 0.000 claims abstract description 78
- -1 polyethylene Polymers 0.000 claims abstract description 78
- 229920000573 polyethylene Polymers 0.000 claims abstract description 78
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 23
- 229910052796 boron Inorganic materials 0.000 claims abstract description 23
- 229910052793 cadmium Inorganic materials 0.000 claims abstract description 15
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims abstract description 15
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims abstract description 11
- 229910052802 copper Inorganic materials 0.000 claims abstract description 11
- 239000010949 copper Substances 0.000 claims abstract description 11
- 239000011133 lead Substances 0.000 claims abstract description 11
- WTEOIRVLGSZEPR-UHFFFAOYSA-N boron trifluoride Chemical compound FB(F)F WTEOIRVLGSZEPR-UHFFFAOYSA-N 0.000 claims abstract description 10
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims abstract description 7
- 229910052721 tungsten Inorganic materials 0.000 claims abstract description 7
- 239000010937 tungsten Substances 0.000 claims abstract description 7
- 229910015900 BF3 Inorganic materials 0.000 claims abstract description 5
- 239000012188 paraffin wax Substances 0.000 claims abstract description 3
- 238000010521 absorption reaction Methods 0.000 claims description 18
- 238000005259 measurement Methods 0.000 claims description 11
- 239000000463 material Substances 0.000 claims description 6
- 239000010410 layer Substances 0.000 description 77
- 230000005855 radiation Effects 0.000 description 10
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 4
- 238000012545 processing Methods 0.000 description 3
- 229910000838 Al alloy Inorganic materials 0.000 description 2
- 239000011241 protective layer Substances 0.000 description 2
- AYCPARAPKDAOEN-LJQANCHMSA-N N-[(1S)-2-(dimethylamino)-1-phenylethyl]-6,6-dimethyl-3-[(2-methyl-4-thieno[3,2-d]pyrimidinyl)amino]-1,4-dihydropyrrolo[3,4-c]pyrazole-5-carboxamide Chemical compound C1([C@H](NC(=O)N2C(C=3NN=C(NC=4C=5SC=CC=5N=C(C)N=4)C=3C2)(C)C)CN(C)C)=CC=CC=C1 AYCPARAPKDAOEN-LJQANCHMSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000004071 biological effect Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
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
- Measurement Of Radiation (AREA)
Abstract
The utility model discloses a wide-energy response neutron dose rate measuring instrument. The wide-energy-response neutron dose rate measuring instrument comprises a spherical thermal neutron proportional counting tube, wherein He-3 gas or enriched boron trifluoride gas is filled in the spherical thermal neutron proportional counting tube; the spherical thermal neutron proportional counting tube is sequentially wrapped with an inner neutron moderating layer, a neutron absorbing layer, a neutron multiplying layer and an outer neutron moderating layer; the neutron moderating layer in the inner layer and the neutron moderating layer in the outer layer are made of polyethylene or paraffin, the neutron absorbing layer is made of boron-containing polyethylene or cadmium, and the neutron multiplying layer is made of lead, copper or tungsten. The neutron dose rate measuring instrument has wide energy response in a neutron energy interval of 0.025 eV-5 GeV, and can measure the neutron dose rate in the neutron energy interval of 0.025 eV-5 GeV. The neutron dose rate measuring instrument meets the requirement of measuring the neutron dose rate of wide energy response.
Description
Technical Field
The utility model relates to a dosimeter, in particular to a wide-energy-response neutron dose rate measuring instrument.
Background
With the continuous development of nuclear technology application and the continuous increase of nuclear facilities, the influence of neutron radiation is more and more important, and the monitoring of neutron radiation dose rate is very important because of the low Oxygen Enhancement Ratio (OER) and high biological effect Ratio (RBE) of neutron to photon radiation, and the harm of neutron radiation to human body is larger than that of photon. However, the current monitoring result of neutron radiation dose rate cannot be satisfied, which is mainly because: the neutron radiation energy range is wide and can reach 11 orders of magnitude, and meanwhile, the interference of photon radiation is accompanied; the standard neutron dose-fluence conversion coefficient varies greatly with neutron energy, with two orders of magnitude difference. The energy of the neutron dose monitored by most neutron dosimeters at present is below 16MeV or 20MeV, and the monitoring requirement of the neutron radiation dose with the neutron energy reaching GeV cannot be met.
Chinese patent application (202021541600.6) discloses a neutron dose equivalent rate measuring device, the device includes base mechanism, signal processing transmission module and measuring mechanism, measuring mechanism includes He-3 proportional counter, go up hemisphere moderator part and lower hemisphere moderator part, he-3 proportional counter is spherical He-3 proportional counter, go up hemisphere moderator part and include the last hemisphere polyethylene protective layer that from inside to outside laid in proper order, go up hemisphere cadmium layer, go up hemisphere aluminum alloy shielding layer and last hemisphere moderator, lower hemisphere moderator part includes the lower hemisphere polyethylene protective layer that from inside to outside laid in proper order, lower hemisphere cadmium layer, lower hemisphere aluminum alloy shielding layer and lower hemisphere moderator, detector sleeve pipe is established to the lower part cover of He-3 proportional counter, signal processing module includes signal processing module and communication module. The device is easy to assemble and can be suitable for neutron dose equivalent rate monitoring in various occasions. However, the device has no high-energy neutron multiplier, can only measure neutron dose rate below 20MeV, and has no wide energy response performance of neutrons above 20 MeV; and the measuring mechanism slowing body of the device can be made of other materials to meet the neutron dose rate measurement requirement.
Disclosure of Invention
The utility model aims to provide a wide-energy response neutron dose rate measuring instrument which has wide-energy response to neutrons of 0.025 eV-5 GeV, can measure the neutron dose rate of the interval of 0.025 eV-5 GeV and meets the measurement requirement of the wide-energy response neutron dose rate.
The utility model discloses a measuring instrument of the neutron dose rate of wide energy response, which comprises a spherical thermal neutron proportional counter tube filled with He-3 gas or enriched boron trifluoride (BF) 3 ) A gas;
the spherical thermal neutron proportional counting tube is sequentially wrapped with an inner neutron moderating layer, a neutron absorbing layer, a neutron multiplying layer and an outer neutron moderating layer;
the neutron moderating layer in the inner layer and the neutron moderating layer in the outer layer are made of polyethylene or paraffin;
the neutron absorption layer is made of boron-containing polyethylene or cadmium;
the neutron multiplication layer is made of lead, copper or tungsten.
Preferably, the neutron absorbing layer is made of boron-containing polyethylene, and when the neutron multiplication layer is made of lead, the neutron moderating layer of the inner layer is made of polyethylene with the thickness of 2.2cm, the neutron absorbing layer is made of polyethylene with the thickness of 0.6cm, the neutron multiplication layer is made of polyethylene with the thickness of 0.8cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 6.3 cm;
the mass content of boron in the boron-containing polyethylene is 10-30% of natural boron.
Preferably, the neutron absorbing layer is made of boron-containing polyethylene, when the neutron multiplying layer is made of copper, the inner neutron moderating layer is made of polyethylene with the thickness of 2.2cm, the neutron absorbing layer is made of polyethylene with the thickness of 0.4cm, the neutron multiplying layer is made of polyethylene with the thickness of 1.1cm, and the outer neutron moderating layer is made of polyethylene with the thickness of 6.4cm.
Preferably, the neutron absorbing layer is made of boron-containing polyethylene, when the neutron multiplication layer is made of tungsten, the neutron moderating layer of the inner layer is made of polyethylene with the thickness of 2.3cm, the neutron absorbing layer is made of polyethylene with the thickness of 0.6cm, the neutron multiplication layer is made of polyethylene with the thickness of 0.4cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 5.8cm.
Preferably, the neutron absorption layer is made of cadmium, when the neutron multiplication layer is made of lead, the neutron moderating layer of the inner layer is made of polyethylene with the thickness of 2.3cm, the neutron absorption layer is made of polyethylene with the thickness of 0.2cm, the neutron multiplication layer is made of polyethylene with the thickness of 0.7cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 6.7 cm;
preferably, a plurality of uniform round holes with the radius of 0.1 cm-0.5 cm are arranged on the neutron absorption layer, for example 114 round holes with the radius of 0.2cm are arranged.
Preferably, the neutron absorption layer is made of cadmium, and when the neutron multiplication layer is made of copper, the neutron moderating layer of the middle inner layer is made of polyethylene with the thickness of 2.2cm, the neutron absorption layer is made of polyethylene with the thickness of 0.3cm, the neutron multiplication layer is made of polyethylene with the thickness of 1.0cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 6.4cm.
The neutron dose rate measuring instrument has wide energy response in a neutron energy interval of 0.025 eV-5 GeV, and can measure the neutron dose rate in the neutron energy interval of 0.025 eV-5 GeV. The neutron dose rate measuring instrument meets the requirement of measuring the neutron dose rate of wide energy response.
Drawings
FIG. 1 is a vertical cross-section of a neutron dose rate measurement instrument of the present utility model.
The figures are marked as follows:
1-an outer neutron moderating layer; 2-neutron multiplication layer; 3-a perforated neutron absorbing layer; 4-an inner neutron moderating layer; 5-spherical thermal neutron proportional counting tube; 6-air.
Fig. 2 is a standard neutron dose-fluence conversion curve given in publication 74 of the international radiation protection committee (ICRP 74 for short) and the energy response curves of five neutron dose rate monitors of the present utility model.
Detailed Description
The present utility model will be further described with reference to the accompanying drawings, but the present utility model is not limited to the following examples.
As shown in fig. 1, the neutron dose rate measuring instrument provided by the utility model comprises an outer neutron moderating layer 1, a neutron multiplying layer 2, a neutron absorbing layer 3, an inner neutron moderating layer 4 and a spherical thermal neutron proportional counter tube 5. The spherical thermal neutron proportional counter tube 5 is filled with He-3 gas or enriched boron trifluoride gas, and an inner neutron moderating layer 4, a perforated neutron absorbing layer 3, a neutron multiplication layer 2 and an outer neutron moderating layer 1 are sequentially wrapped outside the spherical tube 5. The utility model provides five wrapping layers with different materials and thicknesses.
First kind: the spherical pipe is externally arranged 5, and sequentially wraps the inner polyethylene, the boron-containing polyethylene, the lead and the outer polyethylene, wherein the thickness of the inner polyethylene is 2.2cm; the mass of boron in the boron-containing polyethylene is 10 percent, and the thickness is 0.6cm; the thickness of the lead layer is 0.8cm; the outer polyethylene thickness was 6.3cm.
Second kind: the spherical pipe is externally arranged 5, and sequentially wraps the inner polyethylene, the boron-containing polyethylene, the copper and the outer polyethylene, wherein the thickness of the inner polyethylene is 2.2cm; the mass of boron in the boron-containing polyethylene is 10 percent, and the thickness is 0.4cm; the thickness of the copper layer is 1.1cm; the outer polyethylene thickness was 6.4cm.
Third kind: the spherical pipe is externally arranged 5, and sequentially wraps the inner polyethylene, the boron-containing polyethylene, the tungsten and the outer polyethylene, wherein the thickness of the inner polyethylene is 2.3cm; the mass of boron in the boron-containing polyethylene is 10 percent, and the thickness is 0.6cm; the thickness of the tungsten layer is 0.4cm; the outer polyethylene thickness was 5.8cm.
Fourth kind: the spherical pipe is sequentially wrapped with inner polyethylene, cadmium, lead and outer polyethylene. Wherein the thickness of the inner layer polyethylene is 2.3cm; the thickness of the cadmium layer is 0.2cm, and 114 round holes with the radius of 0.2cm are uniformly formed in the cadmium layer; the thickness of the lead layer is 0.7cm; the outer polyethylene thickness was 6.7cm.
Fifth: the spherical pipe is sequentially wrapped with inner polyethylene, cadmium, copper and outer polyethylene. Wherein the thickness of the inner layer polyethylene is 2.2cm; the thickness of the cadmium layer is 0.3cm, and 114 round holes with the radius of 0.2cm are uniformly formed in the cadmium layer; the thickness of the copper layer is 1.0cm; the outer polyethylene thickness was 6.4cm.
As shown in fig. 2, the energy response curves of the above five neutron dose rate measuring instruments and the standard neutron dose-fluence conversion curve given in publication No. 74 of the international radiation protection committee (ICRP 74 for short) are shown, in fig. 2, the horizontal axis represents neutron energy, the vertical axis of the ICRP74 curve represents standard neutron dose-fluence conversion coefficients at different neutron energies, and the vertical axes of the remaining 5 curves represent response values of different neutron energies of the respective neutron dosimeters, respectively.
As can be seen from FIG. 2, five neutron dose rate measurement devices of the present utility model can measure neutron dose rates in a wide energy range of 0.025eV to 5 GeV.
Claims (10)
1. A wide energy response neutron dose rate measuring instrument, characterized in that: comprises a spherical thermal neutron proportional counting tube, wherein He-3 gas or enriched boron trifluoride gas is filled in the counting tube;
the spherical thermal neutron proportional counting tube is sequentially wrapped with an inner neutron moderating layer, a neutron absorbing layer, a neutron multiplying layer and an outer neutron moderating layer.
2. The wide-energy-response neutron dose rate measurement instrument of claim 1, wherein: the neutron moderating layer in the inner layer and the neutron moderating layer in the outer layer are made of polyethylene or paraffin;
the neutron absorption layer is made of boron-containing polyethylene or cadmium;
the neutron multiplication layer is made of lead, copper or tungsten.
3. The wide-energy-response neutron dose rate measurement instrument of claim 2, wherein: the neutron absorption layer is made of boron-containing polyethylene, when the neutron multiplication layer is made of lead, the neutron moderating layer of the inner layer is made of polyethylene with the thickness of 2.2cm, the neutron absorption layer is made of polyethylene with the thickness of 0.6cm, the neutron multiplication layer is made of polyethylene with the thickness of 0.8cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 6.3cm.
4. The wide-energy-response neutron dose rate measurement instrument of claim 2, wherein: the neutron absorption layer is made of boron-containing polyethylene, when the neutron multiplication layer is made of copper, the inner neutron moderating layer is made of polyethylene with the thickness of 2.2cm, the neutron absorption layer is made of polyethylene with the thickness of 0.4cm, the neutron multiplication layer is made of polyethylene with the thickness of 1.1cm, and the outer neutron moderating layer is made of polyethylene with the thickness of 6.4cm.
5. The wide-energy-response neutron dose rate measurement instrument of claim 2, wherein: the neutron absorption layer is made of boron-containing polyethylene, when the neutron multiplication layer is made of tungsten, the neutron moderating layer of the inner layer is made of polyethylene with the thickness of 2.3cm, the neutron absorption layer is made of polyethylene with the thickness of 0.6cm, the neutron multiplication layer is made of polyethylene with the thickness of 0.4cm, and the neutron moderating layer of the outer layer is made of polyethylene with the thickness of 5.8cm.
6. The wide-energy-response neutron dose rate meter of any of claims 2-5, wherein: the mass content of boron in the boron-containing polyethylene is 10-30%.
7. The wide-energy-response neutron dose rate measurement instrument of claim 2, wherein: the material of neutron absorption layer is cadmium, when the material of neutron multiplication layer is lead, the inner neutron moderating layer is polyethylene with thickness of 2.3cm, the thickness of neutron absorption layer is 0.2cm, the thickness of neutron multiplication layer is 0.7cm, and the outer neutron moderating layer is polyethylene with thickness of 6.7cm.
8. The wide-energy-response neutron dose rate measurement instrument of claim 2, wherein: the material of neutron absorption layer is cadmium, when the material of neutron multiplication layer is copper, inlayer neutron moderation layer is the polyethylene of thickness 2.2cm, the thickness of neutron absorption layer is 0.3cm, the thickness of neutron multiplication layer is 1.0cm, outer neutron moderation layer is the polyethylene of thickness 6.4cm.
9. The wide-energy-response neutron dose rate meter of claim 7 or 8, wherein: and a plurality of uniform round holes are formed in the neutron absorption layer.
10. The wide-energy-response neutron dose rate measurement instrument of claim 9, wherein: the radius of the round hole is 0.1 cm-0.5 cm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202321175656.8U CN220085074U (en) | 2023-05-16 | 2023-05-16 | Wide-energy-response neutron dose rate measuring instrument |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202321175656.8U CN220085074U (en) | 2023-05-16 | 2023-05-16 | Wide-energy-response neutron dose rate measuring instrument |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN220085074U true CN220085074U (en) | 2023-11-24 |
Family
ID=88821729
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202321175656.8U Active CN220085074U (en) | 2023-05-16 | 2023-05-16 | Wide-energy-response neutron dose rate measuring instrument |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN220085074U (en) |
-
2023
- 2023-05-16 CN CN202321175656.8U patent/CN220085074U/en active Active
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP5579615B2 (en) | Apparatus for detecting radiation and method for detecting radiation | |
| US8653470B2 (en) | Neutron energy spectrometer | |
| Hertel et al. | The response of Bonner spheres to neutrons from thermal energies to 17.3 MeV | |
| CN102928867B (en) | Compensation type neutron dose instrument | |
| Leake | A spherical dose equivalent neutron detector | |
| CN102928866B (en) | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector | |
| CN107272044A (en) | One kind measurement85Kr interior Gas Filled Detector | |
| US5578830A (en) | Neutron dose equivalent meter | |
| CN220085074U (en) | Wide-energy-response neutron dose rate measuring instrument | |
| CN104898157A (en) | Device and method for measuring neutron dose equivalent | |
| CN102455433A (en) | Method and device for simulating multisphere neutron spectrometer by utilizing position sensitive proportional counter tube | |
| CN101750623B (en) | Portable energy adjusting device for heat energy-100 MeV neutron | |
| CN201047875Y (en) | Modified type A-B neutron ''Rem'' counter | |
| CN214151075U (en) | Neutron-gamma ray information conversion equipment | |
| Strugar et al. | Conversion of the RB reactor neutrons by high-enriched uranium fuel and lithium deuteride | |
| Pálfalvi et al. | Neutron field mapping and dosimetry by CR-39 for radiography and other applications | |
| CN112540397A (en) | Wide-energy neutron dose equivalent rate instrument based on gamma ray energy spectrum detector | |
| CN116594052A (en) | High-range wide-energy response neutron dose rate measuring instrument | |
| CN115201891B (en) | Long neutron counter | |
| CN113504559B (en) | High current pulse wide energy spectrum neutron dose rate monitoring device | |
| Abson et al. | Nuclear-reactor-control ionization chambers | |
| Rosdi et al. | Monte Carlo simulation for designing collimator of neutron diffractometer facility in Malaysia | |
| Yang et al. | Monte Carlo simulation of biological shielding parameters in PGNAA | |
| EP3859404A1 (en) | Lightweight neutron dosimeter | |
| CN214897645U (en) | Power range neutron detector applied to multipurpose modular small reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant |