CN110706833A - One-dimensional experimental device for simulating fission cladding of hybrid reactor - Google Patents
One-dimensional experimental device for simulating fission cladding of hybrid reactor Download PDFInfo
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- CN110706833A CN110706833A CN201910998081.1A CN201910998081A CN110706833A CN 110706833 A CN110706833 A CN 110706833A CN 201910998081 A CN201910998081 A CN 201910998081A CN 110706833 A CN110706833 A CN 110706833A
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- uranium
- hemispherical shell
- based metal
- cladding
- hydrocarbon polymer
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- 238000005253 cladding Methods 0.000 title claims abstract description 35
- 230000004992 fission Effects 0.000 title claims abstract description 28
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 99
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 85
- 229910052751 metal Inorganic materials 0.000 claims abstract description 62
- 239000002184 metal Substances 0.000 claims abstract description 62
- 239000004215 Carbon black (E152) Substances 0.000 claims abstract description 44
- 229930195733 hydrocarbon Natural products 0.000 claims abstract description 44
- 150000002430 hydrocarbons Chemical class 0.000 claims abstract description 44
- 229920000642 polymer Polymers 0.000 claims abstract description 41
- -1 polyethylene Polymers 0.000 claims description 20
- 239000004698 Polyethylene Substances 0.000 claims description 15
- 229920000573 polyethylene Polymers 0.000 claims description 15
- 239000000463 material Substances 0.000 claims description 7
- 239000000843 powder Substances 0.000 claims description 6
- 239000010935 stainless steel Substances 0.000 claims description 5
- 229910001220 stainless steel Inorganic materials 0.000 claims description 5
- 239000004743 Polypropylene Substances 0.000 claims description 4
- 229920001155 polypropylene Polymers 0.000 claims description 4
- 229910001182 Mo alloy Inorganic materials 0.000 claims description 3
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 3
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims description 3
- 239000008187 granular material Substances 0.000 claims description 3
- 239000007788 liquid Substances 0.000 claims description 3
- KTEXACXVPZFITO-UHFFFAOYSA-N molybdenum uranium Chemical compound [Mo].[U] KTEXACXVPZFITO-UHFFFAOYSA-N 0.000 claims description 3
- 239000002861 polymer material Substances 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims description 3
- 238000012360 testing method Methods 0.000 claims description 3
- 229910000439 uranium oxide Inorganic materials 0.000 claims description 3
- NBWXXYPQEPQUSB-UHFFFAOYSA-N uranium zirconium Chemical compound [Zr].[Zr].[U] NBWXXYPQEPQUSB-UHFFFAOYSA-N 0.000 claims description 3
- 239000007769 metal material Substances 0.000 claims description 2
- 229910052739 hydrogen Inorganic materials 0.000 abstract description 13
- 239000001257 hydrogen Substances 0.000 abstract description 13
- 238000013461 design Methods 0.000 abstract description 8
- 230000008901 benefit Effects 0.000 abstract description 5
- 238000012795 verification Methods 0.000 abstract description 5
- ZIMRZUAJVYACHE-UHFFFAOYSA-N uranium;hydrate Chemical compound O.[U] ZIMRZUAJVYACHE-UHFFFAOYSA-N 0.000 abstract description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 6
- 238000002474 experimental method Methods 0.000 description 5
- 238000001514 detection method Methods 0.000 description 4
- 230000003321 amplification Effects 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 238000003199 nucleic acid amplification method Methods 0.000 description 3
- 238000004088 simulation Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 2
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 238000005056 compaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000011888 foil Substances 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 229920001903 high density polyethylene Polymers 0.000 description 1
- 239000004700 high-density polyethylene Substances 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/01—Hybrid fission-fusion nuclear reactors
-
- 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
- Y02E30/10—Nuclear fusion reactors
-
- 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 one-dimensional experimental device for simulating a mixed reactor fission cladding, which comprises an upper rigid hemispherical shell, a lower rigid hemispherical shell, a neutron source target chamber and a uranium-based sleeve, wherein each hemispherical shell comprises a uranium-based metal hemispherical shell and a hydrocarbon polymer hemispherical shell which are concentrically arranged from outside to inside and are sequentially and alternately arranged; the number m of the uranium-based metal hemispherical shells is more than or equal to 2, and the number n of the hydrocarbon polymer hemispherical shells is more than or equal to 1. A uranium-based metal spherical shell, a hydrocarbon polymer spherical shell, a neutron source target chamber and a uranium-based sleeve in the device are assembled into a whole through tolerance fit. The one-dimensional experimental device can better simulate the neutron performance and the closed cladding structure form of the fission cladding of the mixed reactor, realizes the adjustability of the uranium-water ratio (nucleus), meets the verification requirements of different design concepts of the fission cladding of the mixed reactor, has high use efficiency and low verification cost, and has the advantages of engineering realizability, easiness in adjusting the uranium-hydrogen ratio, accuracy in modeling and the like.
Description
Technical Field
The invention belongs to the field of neutron experiments, and particularly relates to a one-dimensional experimental device for simulating a fission cladding of a mixed reactor.
Background
In order to develop a novel energy system, various conceptual designs based on a fusion-fission hybrid subcritical energy reactor (hybrid reactor for short) are provided. As a hybrid stack, the energy magnification M is one of the important physical quantities of physical design concern. The loading of fuel and moderator determines the energy spectrum of the mixing stack, thus directly influencing the energy amplification and burnup. In order to analyze the relationship between the fuels and the moderator, scientists analyze the loading of the fuels and the moderator by using a uranium-water ratio (nucleus) as a characteristic. Whether the concept design is feasible or not, whether the theoretical analysis is reliable or not and how the necessary design margin is judged, and the verification experiment is imperative, and the key point is to establish a one-dimensional experimental device for simulating the fission cladding of the mixed reactor. For example, the design value of the energy amplification factor M of a cladding is 11, and the actual value of the energy amplification factor M of the cladding may be increased to 12 in consideration of safety factor and design reliability. At present, foreign college adopts rectangular lithium piece, graphite piece, has constructed similar experimental apparatus through the mode of building blocks, and it has obvious shortcoming: the precise analysis of the structure is difficult, and the later modeling is not accurate enough. Because the outer boundary and the inner alternate boundary are in special shapes, the structure of the device is difficult to accurately describe in theoretical calculation, and the experimental distribution is difficult.
In summary, there is a need to develop an experimental device for simulating a fission cladding of a mixed reactor, which can solve the defects of inaccurate analysis, easy adjustment of uranium-hydrogen ratio, inaccurate modeling, difficult experimental distribution and the like.
Disclosure of Invention
In view of this, the invention aims to provide a one-dimensional experimental device for simulating a fission cladding of a mixed reactor, which has the advantages of easily adjustable uranium-hydrogen ratio, realizable engineering and accurate modeling.
In order to achieve the purpose, the invention adopts the following technical scheme: a one-dimensional experimental device for simulating a mixed reactor fission cladding is characterized in that: the uranium-based target comprises a uranium-based metal hemispherical shell, a hydrocarbon polymer hemispherical shell, a neutron source target chamber and a uranium-based metal sleeve;
the one-dimensional experimental device comprises an upper hemispherical shell and a lower hemispherical shell which are separated, each hemispherical shell comprises a uranium-based metal hemispherical shell and a hydrocarbon polymer hemispherical shell which are concentrically arranged from outside to inside and are sequentially and alternately arranged, and the innermost hemispherical shell is the uranium-based metal hemispherical shell; the number m of the uranium-based metal hemispherical shells is more than or equal to 2, and the number n of the hydrocarbon polymer hemispherical shells is more than or equal to 1;
the contact surface of the upper rigid hemispherical shell and the lower rigid hemispherical shell is provided with a groove for placing a neutron source target chamber, and the combined uranium-based metal hemispherical shell, hydrocarbon polymer hemispherical shell and neutron source target chamber form a closed sphere; the target head of the neutron source target chamber is positioned in the center of the hemispherical shell;
a uranium-based metal sleeve pointing to the center of the hemispherical shell is fixed in the upper hemispherical shell, and uranium-based plugs and hydrocarbon polymer plugs corresponding to the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell which are arranged in layers with the upper hemispherical shell are placed in the uranium-based metal sleeve;
the uranium-based metal material can be depleted uranium, enriched uranium, uranium oxide, uranium zirconium alloy and uranium molybdenum alloy according to experimental test requirements. The hydrocarbon polymer material can be polyethylene and polypropylene.
Preferably, the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell are rigid solid structures.
Preferably, the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell are rigid hollow and are filled with one structure of liquid, powder or granular materials.
Preferably, the thickness range of the uranium-based metal hemispherical shell is 4cm ~ 5cm, and the thickness range of the hydrocarbon polymer hemispherical shell is 1c ~ 3 cm.
Preferably, the material of the neutron source target chamber is stainless steel.
Preferably, the top end of the uranium-based metal sleeve is fixed through a clamping ring, and the diameter of the tail end of the uranium-based metal sleeve is reduced and closed.
Preferably, the thickness range of the uranium-based plugs and hydrocarbon polymer plugs is 5mm ~ 20 mm.
The one-dimensional experimental device for simulating the mixed reactor fission cladding can better simulate the neutronics performance and the closed cladding structure form of the mixed reactor fission cladding, realize the adjustment of the uranium-hydrogen ratio and meet the verification requirements of different mixed reactor fission cladding design concepts. The one-dimensional experimental device for simulating the mixed reactor fission cladding has the advantages of high use efficiency, low verification cost, engineering realization, easiness in adjusting the uranium-hydrogen ratio, accuracy in modeling and the like.
Drawings
FIG. 1 is a schematic structural diagram of a one-dimensional experimental apparatus for simulating a fission cladding of a hybrid reactor according to the present invention;
FIG. 2 is a schematic structural diagram of a uranium-based metal sleeve in a one-dimensional experimental device for simulating a mixed reactor fission cladding according to the invention;
in the figure, 1, a uranium-based metal hemispherical shell 2, a hydrocarbon polymer hemispherical shell 3, a neutron source target chamber 4, a uranium-based metal sleeve 5, a uranium-based metal plug 6 and a hydrocarbon polymer plug are arranged.
Detailed Description
The invention is further described below with reference to the figures and examples.
As shown in FIG. 1, the one-dimensional experimental device for simulating the fission cladding of the mixed reactor comprises a uranium-based metal hemispherical shell, a hydrocarbon polymer hemispherical shell, a neutron source target chamber and a uranium-based metal sleeve; the one-dimensional experimental device comprises an upper hemispherical shell and a lower hemispherical shell which are separated, each hemispherical shell comprises a uranium-based metal hemispherical shell and a hydrocarbon polymer hemispherical shell which are concentrically arranged from outside to inside and are sequentially and alternately arranged, and the innermost hemispherical shell is the uranium-based metal hemispherical shell; the number m of the uranium-based metal hemispherical shells is more than or equal to 2, and the number n of the hydrocarbon polymer hemispherical shells is more than or equal to 1;
the contact surface of the upper rigid hemispherical shell and the lower rigid hemispherical shell is provided with a groove for placing a neutron source target chamber, and the combined uranium-based metal hemispherical shell, hydrocarbon polymer hemispherical shell and neutron source target chamber form a closed sphere; the target head of the neutron source target chamber is positioned in the center of the hemispherical shell;
a uranium-based metal sleeve pointing to the center of the hemispherical shell is fixed in the upper hemispherical shell, and uranium-based plugs and hydrocarbon polymer plugs corresponding to the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell which are arranged in layers with the upper hemispherical shell are placed on the uranium-based metal sleeve; according to experimental test requirements, replacing uranium-based plugs or hydrocarbon polymer plugs at positions to be distributed with detection media.
In order to solve the problems of easy adjustment of hydrogen-hydrogen ratio of uranium and realized engineering, the adjustment of a uranium material can be realized by using uranium-based metals such as depleted uranium, enriched uranium, uranium oxide, uranium zirconium alloy and uranium molybdenum alloy, and the adjustment of a hydrogen material is realized by using hydrocarbon polymer materials such as polyethylene, polypropylene and the like. Meanwhile, the function of easily adjusting the ratio (nucleus) of uranium to hydrogen is substantially solved by adjusting the density and the components by means of the forms of powder, particles and the like.
The one-dimensional experimental device for simulating the mixed reactor fission cladding utilizes the advantages that the moderation characteristics of polyethylene and water are similar and the engineering is easy to realize, and utilizes hydrocarbon polymer to replace water to simulate cooling water in the mixed reactor cladding; based on the advantage of a totally-enclosed rigid structure of the spherical shell, the structure and the uranium-water ratio of a mixed reactor cladding are simulated by utilizing the alternate combination configuration of the spherical shell; eliminating environmental influence by adding a shielding layer; arranging a neutron source target chamber through grooves on the end surfaces of the upper hemispherical shell and the lower hemispherical shell; the detection medium is disposed through a uranium-based metal sleeve.
The uranium-based metal hemispherical shell is a metal part of the device and simulates a cracking part in the cladding. The hydrocarbon polymer hemisphere shell uses high density polyethylene to simulate cooling water. The proportion of uranium materials and cooling water in the mixed reactor fission cladding is simulated through the material nuclear-seed ratio of the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell.
During the experiment, the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell are combined into a lower hemispherical shell according to the experiment requirement, and the lower hemispherical shell is placed on the circular tray frame; the lower hemispherical shell is lifted and matched with the neutron source target chamber, so that the target head is positioned at the center of the lower hemispherical shell; installing the upper hemispherical shell according to the sequence corresponding to the lower hemispherical shell; and a chock block and a detection medium are arranged in the uranium metal sleeve, and the uranium metal sleeve is limited and fixed through a clamping ring.
In a preferred embodiment, the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell are selected to be rigid solid structures, and accurate measurement of the radius of the hemispherical shell is guaranteed through the rigid one-dimensional characteristic, so that the modeling accuracy of the simulation device is improved, self-support is realized, and the use efficiency, particularly the assembly efficiency, in the experiment implementation process is improved.
In another preferred embodiment, in order to achieve the above effect of improving the modeling accuracy of the simulation device, the uranium-based metal hemispherical shell and the hydrocarbon polymer hemispherical shell may also be selected from rigid hollow shells and filled with one structure of liquid, powder or granular materials.
More preferably, the thickness of the uranium-based metal hemispherical shell is 4 ~ 5cm, and the thickness of the hydrocarbon polymer hemispherical shell is 1 ~ 3 cm.
Further preferably, the material of the neutron source target chamber is stainless steel.
Preferably, the top end of the uranium-based metal sleeve is fixed through a clamping ring, and the tail end of the uranium-based metal sleeve is reduced in diameter and closed.
In order to further improve the modeling accuracy of the simulation device, the alternating structure of the uranium-based plugs and the hydrocarbon polymer plugs in the uranium-based metal sleeve is designed to be consistent with the alternating structure of the hemispherical shell, the thickness ranges of the uranium-based plugs and the hydrocarbon polymer plugs are set to be 5mm ~ 20mm, and the technical effects are achieved through the combination of the plugs with different thicknesses.
Example 1
The one-dimensional experimental device for verifying the fission cladding of the mixed reactor comprises depleted uranium hemispherical shells with inner/outer diameters (unit: mm) of 131/181, 194/233 and 254/300, polyethylene hemispherical shells with inner/outer diameters (unit: mm) of 181/194 and 233/254, a neutron source chamber with outer diameter of 38mm, a depleted uranium sleeve with inner/outer diameter (unit: mm) of 32/44, a depleted uranium plug block with outer diameter of 32mm and thickness of 2-20mm and a polyethylene plug block with outer diameter of 32mm and thickness of 2-20mm, wherein the depleted uranium metal hemispherical shells and the polyethylene hemispherical shells are combined up and down, and the end face combination is guaranteed to be flat, and the size has the requirement of small clearance fit tolerance. The assembly method is as follows: the thickness of the uranium spherical shell and the thickness of the polyethylene spherical shell are designed according to the required uranium-hydrogen ratio, and the lower half parts of depleted uranium hemispherical shells and polyethylene hemispherical shells are sequentially placed on the metal tray frame; lifting the lower hemispherical shell, and placing the neutron source target chamber in the center of the spherical shell; placing the upper half parts of depleted uranium hemispherical shells and polyethylene hemispherical shells onto the lower half parts from inside to outside, and ensuring that complete spherical shells are formed; the uranium-based metal sleeve is filled in through a depleted uranium hemispherical shell and a pore channel of the upper half part of a polyethylene hemispherical shell and is fixed through a snap ring; filling depleted uranium plugs and polyethylene plugs into the sleeve, and ensuring that the plugs in the sleeve correspond to the spherical shell. Depleted uranium metal foil with a thickness of 0.2mm is added as a detection medium between uranium-based plugs or polyethylene plugs at five positions within the sleeve from the centre of the sphere of 156mm, 189mm, 215mm, 244mm, 279 mm. The experimental setup thus constructed had a uranium to hydrogen ratio (nuclei) of about 2.24: 1.
Example 2
In example 1, if all depleted uranium hemisphere shells were replaced with stainless steel ball shells of 2mm thickness, the interior was filled with uranium dioxide powder. The density of the uranium dioxide powder in the stainless steel shell can reach 3.0g/cm after repeated compaction3Density of 18.3g/cm compared to depleted uranium3The amplitude reduction exceeds 80 percent. The experimental setup thus constructed had a uranium to hydrogen ratio (nuclei) of about 0.37: 1.
Example 3
In example 1, a polyethylene spherical shell having an inner/outer diameter (unit: mm) of 111/131 and an inner/outer diameter (unit: mm) of 300/350 was added to the inside thereof. The experimental setup thus constructed changed the uranium to hydrogen ratio (nuclei) to 0.52: 1.
Example 4
In example 1, if the polyethylene is replaced by polypropylene with a density of 0.90 (C) without changing the structure4H6). The experimental setup thus constructed changed the uranium to hydrogen ratio (nuclei) to 3.14: 1.
It should be noted that the above description is only intended to illustrate some of the principles of the experimental setup of the present invention. Since numerous modifications and variations will readily occur to those skilled in the art, it is not desired to limit the invention to the exact construction and operation illustrated and described, and accordingly, all suitable modifications and equivalents may be resorted to, falling within the scope of the invention.
Claims (8)
1. A one-dimensional experimental device for simulating a mixed reactor fission cladding is characterized in that: the uranium-based target comprises a uranium-based metal hemispherical shell (1), a hydrocarbon polymer hemispherical shell (2), a neutron source target chamber (3) and a uranium-based metal sleeve (4);
the one-dimensional experimental device comprises an upper hemispherical shell and a lower hemispherical shell which are separated, each hemispherical shell comprises a uranium-based metal hemispherical shell (1) and a hydrocarbon polymer hemispherical shell (2) which are concentrically arranged from outside to inside and are sequentially and alternately arranged, and the innermost hemispherical shell is the uranium-based metal hemispherical shell (1); the number m of the uranium-based metal hemispherical shells (1) is more than or equal to 2, and the number n of the layers of the hydrocarbon polymer hemispherical shells (2) is more than or equal to 1;
the contact surface of the upper rigid hemispherical shell and the lower rigid hemispherical shell is provided with a groove for placing a neutron source target chamber (3), and the combined uranium-based metal hemispherical shell (1), hydrocarbon polymer hemispherical shell (2) and neutron source target chamber (3) form a closed sphere; the target head of the neutron source target chamber (3) is positioned in the center of the hemispherical shell;
a uranium-based metal sleeve (4) pointing to the center of the hemispherical shell is fixed in the upper hemispherical shell, and uranium-based metal hemispherical shells (1) and uranium-based plugs (5) and hydrocarbon polymer plugs (6) which are arranged in layers with the upper hemispherical shell and correspond to the hydrocarbon polymer hemispherical shell (2) are arranged in the uranium-based metal sleeve (4);
the uranium-based metal material can be depleted uranium, enriched uranium, uranium oxide, uranium zirconium alloy and uranium molybdenum alloy according to experimental test requirements;
the hydrocarbon polymer material can be polyethylene and polypropylene.
2. The one-dimensional experimental apparatus for simulating a hybrid reactor fission cladding of claim 1, wherein: the uranium-based metal hemispherical shell (1) and the hydrocarbon polymer hemispherical shell (2) are rigid solid structures.
3. The one-dimensional experimental apparatus for simulating a hybrid reactor fission cladding of claim 1, wherein: the uranium-based metal hemispherical shell (1) and the hydrocarbon polymer hemispherical shell (2) are rigid hollow and are filled with one of liquid, powder or granular materials.
4. The one-dimensional experimental device for simulating the mixed reactor fission cladding as claimed in claim 1, wherein the thickness of the layer of the uranium-based metal hemispherical shell (1) is in a range of 4cm ~ 5 cm.
5. The one-dimensional experimental device for simulating the fission cladding of the hybrid reactor according to claim 4, wherein the layer thickness of the hydrocarbon polymer hemispherical shell (2) ranges from 1cm ~ 3 cm.
6. The one-dimensional experimental apparatus for simulating a hybrid reactor fission cladding of claim 1, wherein: the material of the neutron source target chamber (3) is stainless steel.
7. The one-dimensional experimental apparatus for simulating a hybrid reactor fission cladding of claim 1, wherein: the top of uranium-based metal sleeve (4) pass through the snap ring fixed, the tail end diameter of uranium-based metal sleeve (4) reduces and seals.
8. The one-dimensional experimental device for simulating the hybrid reactor fission cladding as claimed in claim 1, wherein the thickness range of the uranium-based plug (5) and the hydrocarbon polymer plug (6) is 5mm ~ 20 mm.
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1996041769A1 (en) * | 1995-06-13 | 1996-12-27 | Patterson James A | Improved system and method for electrolysis and heating of water |
| CN106158052A (en) * | 2015-03-18 | 2016-11-23 | 董沛 | The spherical primary tank of concentric spherical iris type |
| CN210896639U (en) * | 2019-10-21 | 2020-06-30 | 中国工程物理研究院核物理与化学研究所 | One-dimensional experimental device for simulating fission cladding of hybrid reactor |
-
2019
- 2019-10-21 CN CN201910998081.1A patent/CN110706833A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1996041769A1 (en) * | 1995-06-13 | 1996-12-27 | Patterson James A | Improved system and method for electrolysis and heating of water |
| CN106158052A (en) * | 2015-03-18 | 2016-11-23 | 董沛 | The spherical primary tank of concentric spherical iris type |
| CN210896639U (en) * | 2019-10-21 | 2020-06-30 | 中国工程物理研究院核物理与化学研究所 | One-dimensional experimental device for simulating fission cladding of hybrid reactor |
Non-Patent Citations (3)
| Title |
|---|
| 严小松: ""14MeV中子与贫铀聚乙烯球壳装置作用的铀反应率研究"", 中国优秀硕士学位论文全文数据库工程科技Ⅱ辑, no. 3, 15 March 2013 (2013-03-15), pages 12 - 15 * |
| 严小松;刘荣;鹿心鑫;蒋励;王玫;林菊芳;: "贫化铀/聚乙烯球壳交替系统中铀-238中子俘获率的测量与分析", 物理学报, no. 10, 23 May 2012 (2012-05-23) * |
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