CN116913573B - Neutron beam-gathering device - Google Patents
Neutron beam-gathering device Download PDFInfo
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- CN116913573B CN116913573B CN202310954159.6A CN202310954159A CN116913573B CN 116913573 B CN116913573 B CN 116913573B CN 202310954159 A CN202310954159 A CN 202310954159A CN 116913573 B CN116913573 B CN 116913573B
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- neutron
- coating
- neutron beam
- graphite tube
- graphite
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- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 28
- 229910002804 graphite Inorganic materials 0.000 claims abstract description 25
- 239000010439 graphite Substances 0.000 claims abstract description 25
- 239000011248 coating agent Substances 0.000 claims abstract description 17
- 238000000576 coating method Methods 0.000 claims abstract description 17
- 229910052580 B4C Inorganic materials 0.000 claims description 5
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 5
- 238000000034 method Methods 0.000 claims description 4
- 238000005245 sintering Methods 0.000 claims description 3
- 206010028980 Neoplasm Diseases 0.000 claims description 2
- 230000004992 fission Effects 0.000 claims description 2
- 230000004927 fusion Effects 0.000 claims description 2
- 230000008569 process Effects 0.000 claims description 2
- 201000011510 cancer Diseases 0.000 claims 1
- 230000000694 effects Effects 0.000 abstract description 5
- 239000000463 material Substances 0.000 description 15
- 238000010521 absorption reaction Methods 0.000 description 11
- 239000000047 product Substances 0.000 description 5
- 230000004907 flux Effects 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 3
- 229910052799 carbon Inorganic materials 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- -1 polytetrafluoroethylene Polymers 0.000 description 3
- 229910052726 zirconium Inorganic materials 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 239000011824 nuclear material Substances 0.000 description 2
- 229920001343 polytetrafluoroethylene Polymers 0.000 description 2
- 239000004810 polytetrafluoroethylene Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 239000004698 Polyethylene Substances 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000005672 electromagnetic field Effects 0.000 description 1
- 239000012467 final product Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 230000003902 lesion Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 239000011163 secondary particle Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000013077 target material Substances 0.000 description 1
- 238000002834 transmittance Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21K—TECHNIQUES FOR HANDLING PARTICLES OR IONISING RADIATION NOT OTHERWISE PROVIDED FOR; IRRADIATION DEVICES; GAMMA RAY OR X-RAY MICROSCOPES
- G21K1/00—Arrangements for handling particles or ionising radiation, e.g. focusing or moderating
- G21K1/02—Arrangements for handling particles or ionising radiation, e.g. focusing or moderating using diaphragms, collimators
-
- 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
Abstract
The invention discloses a neutron beam-gathering device, which comprises a graphite tube body and B 4 C, coating; the whole graphite tube body is approximately Y-shaped and comprises a cone body and a cylinder body, wherein the inclination angle alpha of the cone body is 5.71 ℃, and the height of the cylinder body is 1/10 of the whole height of the graphite tube body along the axial direction; the length ratio of the inner diameter D1 of the hole of the column body to the inner diameter D2 of the upper opening of the cone body is 1:10; the coating on the outer surface of the graphite tube body has the mass thickness of 0.2g/cm 2 B of (2) 4 And C, coating. Through the neutron beam-gathering device, a collimated neutron beam can be obtained, so that the emitted neutrons have a certain directivity; the bunching can be up to 44 times (for neutron reactors). The neutron source has collimation effect, and the neutron utilization efficiency is improved.
Description
Technical Field
The invention belongs to the field of special material equipment manufacturing, and particularly relates to a neutron beam buncher.
Background
Since neutrons are not charged, electromagnetic fields cannot be used to confine neutrons to a neutron beam, and neutron behavior has been described using neutron diffusion methods. The neutron and target are separated into scattering and absorbing, and the neutron has its transverse momentum lowered gradually to reach the aim of beam focusing.
So far, no neutron beam focusing device has been found.
The neutron beam-gathering device has important significance for the efficient utilization of neutrons, and plays a great role in the application of utilizing neutrons to irradiation material research and boron neutron capture treatment of cancers (BNCT), fission stacks and fusion stacks.
Disclosure of Invention
The invention aims to solve the problem that no neutron beam-gathering device exists at present, and develops a graphite neutron beam-gathering device.
The invention aims at realizing the following technical measures:
the technical proposal is as follows: a neutron beam gathering device comprises a graphite tube body and B 4 And C, coating.
Wherein the tube body is a cone body part with the thickness of 5cm and a cylinder body part with the thickness of 5cm, and the cone inclination angle alpha (shown as a schematic diagram of a neutron beam buncher) is 5.71 ℃; the inner diameter D1 of the cylinder hole is 1cm, and the inner diameter D2 of the upper opening of the cone is 10cm; the height H1 of the column body is 5cm, the through height H of the column body and the graphite body is 50cm, and the mass thickness of the coating on the outer surface of the graphite body structure is 0.2g/cm 2 Boron carbide (B) 4 C）。
Material requirements and manufacturing methods: selecting high-purity graphite with purity of more than 99.9%, preparing blanks according to a schematic structure of a buncher, and compacting (aiming at improving the density of a finished product); coating boron carbide on the outer surface of graphite blank, B 4 The mass thickness of C is 0.2g/cm 2 The coating is added for absorbing neutrons and playing a role of protection and shielding; and (5) sintering at high temperature.
Advantages of neutron beam buncher: the collimated neutron beam can be obtained, so that the outgoing neutrons have a certain directivity; the bunching can be up to 44 times (for neutron reactors). The neutron source has collimation effect, and the neutron utilization efficiency is improved.
Drawings
FIG. 1 is a schematic diagram of a neutron beam combiner of the present invention.
Detailed Description
The present invention will be specifically described below by way of examples. It is noted herein that the following examples are given solely for the purpose of illustration and are not to be construed as limiting the scope of the invention, as many insubstantial modifications and variations of the invention will become apparent to those skilled in the art in light of the above disclosure.
Example 1:
example 1:
first, material selection:
in order to obtain higher bunching degree, a nuclear material with a small neutron absorption section and a large scattering section is selected, and the nuclear material has a larger material density, namely a material with a small macroscopic absorption section and a large macroscopic scattering section; solid at normal temperature and high melting point; the simple substances, compounds or mixtures of such materials are desirably carbon, zirconium and polytetrafluoroethylene. Zirconium is easy to generate hydrogen embrittlement in a neutron field, the service life of the zirconium serving as a neutron beam buncher is short, the price is high, and materials are not easy to obtain; polytetrafluoroethylene has small density and small macroscopic absorption cross section (the thickness is too large by using the material), and is not suitable for use. Graphite is thus ultimately chosen as the structural material for the neutron beam buncher.
Second, the inclination angle of the vertebral bodyIs determined by:
scattering angleAs known from the physical analysis theory of nuclear reactor, the average value of the cosine of the scattering angle is +.>Wherein A is the target mass number. It can be found that the average scattering angle of neutrons for the carbon target is 86.82 degrees (designated critical angle +.>) Close to isotropic but still with a slight forward scattering effect. If the scattered neutrons are isotropically distributed, half of the neutrons will be scattered back into the beam-concentrator before reaching the surface, this assumption needs to be accounted for by two losses, one being the loss of neutron absorption by the material and the other being the transmission loss without any scattering.
Angle theta between scattered neutrons and external surface of beam-gathering device L The value range is alpha-90+alpha; when the scattering angle is smaller than theta L When neutrons will not be possible to return to the beam-buncher due to the angular relationship, i.e. this part of the neutrons are lost entirely.
Defining the non-angle loss probability as:
according to the above formula, the smaller the cone inclination angle alpha is, the better, but the smaller the angle is, the larger the length is needed, and the alpha is selected to be 5.71. The critical angle theta of the carbon is hereby summed C The non-angle loss probability can be found as:。
third, determination of thickness.
The thickness of the graphite affects the extent to which neutrons are absorbed by the material and the extent to which neutrons are transmitted. The non-absorption probability is defined as:
where t is the wall thickness of the beam-forming device, and gamma is the angle between the incoming neutron and the inward normal of the wall (as shown in the schematic diagram of the beam-forming device).
The non-perspective probability (i.e., the effective scattering probability) is defined as:
as can be seen from the above two analyses, as the thickness increases, P 2 Will decrease, P 3 Will increase, and selecting a suitable thickness may maximize their product, with the thickness at this time being referred to as the optimal thickness. The optimal thickness is selected according to the incident angle, and the wall thickness is finally determined to be 5cm by taking the proper incident angle (such as 60 ℃ C.). The further increase in thickness is not significant in improving the overall bunching effect. Obtaining P according to the above parameters 2 =0.994，P 3 =0.979。
Fourth, the bunching degree is determined.
Probability P of isotropically scattered neutrons returning into the beam shaper 4 =0.5.
When the neutrons in the beam-gathering device reach a steady state (the process can be completed in the moment), the neutron flux density and the cross section area at the outlet are multiplied according to a neutron conservation equationThe product is equal to the product of neutron flux density at the inlet and cross-sectional area multiplied by P 1 、P 2 、P 3 、P 4 . Neutron decay itself is negligible due to the short transit time.
Therefore, according to the definition of the bunching degree, the bunching degree is calculated as:
s in the above 1 、S 2 The opening areas of the beam combiner outlet and inlet, respectively. The degree of bunching was found to be k=43.8 by substituting the four probabilities described above for the designed D1 and D2.
Fifth, B 4 And C, determining the thickness of the coating.
Boron has a large thermal neutron absorption cross section, in which 10 B plays an important role. According to B 4 The macroscopic absorption section of the C density, the molecular weight and the neutron microscopic absorption section data can be obtained, and then the macroscopic absorption section is calculated according to the designed graphite thickness and B 4 And the thickness C is calculated by combining a proper angle, so that the average transmittance of neutrons to the beam-forming device is less than three thousandths. Furthermore, the processing unit is configured to, 10 b secondary particles alpha and alpha generated after neutron absorption 7 Li is self-absorbed by the material itself and does not penetrate the walls. Therefore B 4 The shielding protection effect of the C coating is good. Even so, the operator should take other shielding precautions.
Material requirements and manufacturing methods: selecting high-purity graphite with purity of more than 99.9%, preparing blanks according to a schematic structure of a buncher, and compacting (aiming at improving the density of a finished product); coating boron carbide on the outer surface of graphite blank, B 4 The mass thickness of C is 0.2g/cm 2 The coating is added for absorbing neutrons and playing a role of protection and shielding; sintering at high temperature to obtain the final product.
As shown in FIG. 1, a neutron beam focusing device comprises a graphite tube body and B 4 The C coating, wherein the tube body is a cone body part with the thickness of 5cm and a cylinder body part with the thickness of 5cm, and the cone inclination angle alpha is 5.71 ℃; the inner diameter D1 of the column body hole is 1cm, and the inner diameter D2 of the upper opening of the cone body is10cm; the height H1 of the column body is 5cm, the through height H of the column body and the graphite body is 50cm, and the mass thickness of the coating on the outer surface of the graphite body structure is 0.2g/cm 2 Boron carbide (B) 4 C）。
Notice that: don't cut B 4 C is applied to the inner surface or the upper and lower mouth surface positions and is to be prevented from being coated with B 4 C, pollution; the neutron beam is kept taking care that it cannot be contaminated by substances with large neutron absorption cross sections.
The using method comprises the following steps: the opening (i.e. the inlet) of the neutron beam buncher is opposite to the neutron source outlet (such as a neutron reactor), if the neutron beam buncher needs to be sealed and bear pressure, the upper opening of the cone part can be matched with a flange for use by adding an external edge (with proper thickness) during blank making; if the neutron radiation source is used, the radiation source can be arranged in the beam-bunching device, the normal line of the forward direction of the radiation source coincides with the axis of the outlet, and the rear part of the radiation source can be firmly plugged by polyethylene materials. The beam-forming device orifice (i.e., exit) is directed toward the target material or lesion.
The bunching degree is defined as: the ratio of the neutron flux density at the exit to the neutron flux density at the entrance.
The preferred embodiments of the present invention have been described in detail above, but the present invention is not limited to the specific details of the above embodiments, and various equivalent changes can be made to the technical solution of the present invention within the scope of the technical concept of the present invention, and all the equivalent changes belong to the protection scope of the present invention.
In addition, the specific features described in the above embodiments may be combined in any suitable manner without contradiction. The various possible combinations of the invention are not described in detail in order to avoid unnecessary repetition. Moreover, any combination of the various embodiments of the invention can be made without departing from the spirit of the invention, which should also be considered as disclosed herein.
Claims (4)
1. A neutron beam-gathering device is characterized by comprising a graphite tube body and B 4 C, coating;
the whole graphite tube body is approximately Y-shaped and comprises a cone body and a cylinder body, wherein the inclination angle alpha of the cone body is 5.71 ℃, and the height of the cylinder body is 1/10 of the whole height of the graphite tube body along the axial direction; the length ratio of the inner diameter D1 of the hole of the column body to the inner diameter D2 of the upper opening of the cone body is 1:10;
the coating on the outer surface of the graphite tube body has the mass thickness of 0.2g/cm 2 B of (2) 4 And C, coating.
2. The neutron beam device of claim 1, wherein the graphite tube has a wall thickness of 5cm.
3. The method of claim 1, comprising the steps of:
selecting high-purity graphite with purity of more than 99.9%, preparing blanks according to a buncher structure, and compacting, wherein granularity is 200 meshes; coating boron carbide on the outer surface of graphite blank, B 4 The mass thickness of C is 0.2g/cm < 2 >; and (5) sintering at high temperature.
4. Use of a neutron beam buncher obtainable by the process of claim 3 in the treatment of cancer, fission and fusion piles.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202310954159.6A CN116913573B (en) | 2023-08-01 | 2023-08-01 | Neutron beam-gathering device |
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| CN202310954159.6A CN116913573B (en) | 2023-08-01 | 2023-08-01 | Neutron beam-gathering device |
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| CN116913573B true CN116913573B (en) | 2024-01-23 |
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