CN114672086A - Neutron poison storage tank material and preparation method thereof, and neutron poison storage tank - Google Patents
Neutron poison storage tank material and preparation method thereof, and neutron poison storage tank Download PDFInfo
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- CN114672086A CN114672086A CN202210230829.5A CN202210230829A CN114672086A CN 114672086 A CN114672086 A CN 114672086A CN 202210230829 A CN202210230829 A CN 202210230829A CN 114672086 A CN114672086 A CN 114672086A
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- 239000000463 material Substances 0.000 title claims abstract description 96
- 238000003860 storage Methods 0.000 title claims abstract description 66
- 239000002574 poison Substances 0.000 title claims abstract description 56
- 231100000614 poison Toxicity 0.000 title claims abstract description 56
- 238000002360 preparation method Methods 0.000 title abstract description 9
- -1 polyethylene Polymers 0.000 claims abstract description 59
- 239000004698 Polyethylene Substances 0.000 claims abstract description 55
- 229920000573 polyethylene Polymers 0.000 claims abstract description 55
- 229910052580 B4C Inorganic materials 0.000 claims abstract description 25
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims abstract description 25
- 238000000034 method Methods 0.000 claims description 24
- 238000001125 extrusion Methods 0.000 claims description 23
- 238000002156 mixing Methods 0.000 claims description 21
- 238000001816 cooling Methods 0.000 claims description 20
- 230000008569 process Effects 0.000 claims description 16
- 238000003756 stirring Methods 0.000 claims description 12
- 238000003754 machining Methods 0.000 claims description 10
- 238000000465 moulding Methods 0.000 claims description 10
- 239000000843 powder Substances 0.000 claims description 10
- 238000007723 die pressing method Methods 0.000 claims description 6
- 239000003963 antioxidant agent Substances 0.000 claims description 4
- 230000003078 antioxidant effect Effects 0.000 claims description 4
- 230000006835 compression Effects 0.000 claims description 4
- 238000007906 compression Methods 0.000 claims description 4
- 239000007822 coupling agent Substances 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 238000000265 homogenisation Methods 0.000 claims description 3
- 239000000203 mixture Substances 0.000 claims description 3
- 238000003825 pressing Methods 0.000 claims description 3
- 238000010521 absorption reaction Methods 0.000 abstract description 8
- 239000002253 acid Substances 0.000 abstract description 6
- 230000005484 gravity Effects 0.000 abstract description 6
- 238000012545 processing Methods 0.000 abstract description 6
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- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 32
- 229910052796 boron Inorganic materials 0.000 description 32
- 229910052778 Plutonium Inorganic materials 0.000 description 11
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 11
- 238000012360 testing method Methods 0.000 description 11
- 239000007788 liquid Substances 0.000 description 9
- 239000004568 cement Substances 0.000 description 7
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 6
- 239000001257 hydrogen Substances 0.000 description 6
- 229910052739 hydrogen Inorganic materials 0.000 description 6
- 230000007797 corrosion Effects 0.000 description 4
- 238000005260 corrosion Methods 0.000 description 4
- 239000004615 ingredient Substances 0.000 description 4
- 229910052688 Gadolinium Inorganic materials 0.000 description 3
- 230000032683 aging Effects 0.000 description 3
- 238000005452 bending Methods 0.000 description 3
- 229910052793 cadmium Inorganic materials 0.000 description 3
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 3
- 230000008859 change Effects 0.000 description 3
- 238000005520 cutting process Methods 0.000 description 3
- 238000001514 detection method Methods 0.000 description 3
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 3
- 230000035882 stress Effects 0.000 description 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 2
- 239000004699 Ultra-high molecular weight polyethylene Substances 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 229910017604 nitric acid Inorganic materials 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000012958 reprocessing Methods 0.000 description 2
- 238000007493 shaping process Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229920000785 ultra high molecular weight polyethylene Polymers 0.000 description 2
- ZOXJGFHDIHLPTG-BJUDXGSMSA-N Boron-10 Chemical compound [10B] ZOXJGFHDIHLPTG-BJUDXGSMSA-N 0.000 description 1
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000002671 adjuvant Substances 0.000 description 1
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- 238000011160 research Methods 0.000 description 1
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- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
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- 238000003878 thermal aging Methods 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 description 1
- 238000013024 troubleshooting Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
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Classifications
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- C—CHEMISTRY; METALLURGY
- C08—ORGANIC MACROMOLECULAR COMPOUNDS; THEIR PREPARATION OR CHEMICAL WORKING-UP; COMPOSITIONS BASED THEREON
- C08L—COMPOSITIONS OF MACROMOLECULAR COMPOUNDS
- C08L23/00—Compositions of homopolymers or copolymers of unsaturated aliphatic hydrocarbons having only one carbon-to-carbon double bond; Compositions of derivatives of such polymers
- C08L23/02—Compositions of homopolymers or copolymers of unsaturated aliphatic hydrocarbons having only one carbon-to-carbon double bond; Compositions of derivatives of such polymers not modified by chemical after-treatment
- C08L23/04—Homopolymers or copolymers of ethene
- C08L23/06—Polyethene
-
- C—CHEMISTRY; METALLURGY
- C08—ORGANIC MACROMOLECULAR COMPOUNDS; THEIR PREPARATION OR CHEMICAL WORKING-UP; COMPOSITIONS BASED THEREON
- C08L—COMPOSITIONS OF MACROMOLECULAR COMPOUNDS
- C08L2205/00—Polymer mixtures characterised by other features
- C08L2205/02—Polymer mixtures characterised by other features containing two or more polymers of the same C08L -group
- C08L2205/025—Polymer mixtures characterised by other features containing two or more polymers of the same C08L -group containing two or more polymers of the same hierarchy C08L, and differing only in parameters such as density, comonomer content, molecular weight, structure
Abstract
The invention provides a neutron poison storage tank material, a preparation method thereof and a neutron poison storage tank, wherein the neutron poison storage tank material comprises a main material, and the main material comprises the following components in parts by mass: 0.5 to 35 percent of boron carbide, and the balance of polyethylene and polyethylene wax; wherein the mass of the polyethylene wax is 0.5-20% of that of the polyethylene. The material has good neutron absorption performance, excellent physicochemical and mechanical properties, high and adjustable hydroboron content and small specific gravity, and meets the processing and forming requirements of different shapes, thereby ensuring the critical safety of the storage tank. The material can be suitable for the use environment with high acid, high temperature and strong irradiation, and can achieve the effects of reducing the plant load, increasing the storage volume and reducing the investment cost of a factory.
Description
Technical Field
The invention particularly relates to a neutron poison storage tank material, a preparation method thereof and a neutron poison storage tank.
Background
In a spent fuel reprocessing Purex (one of nuclear fuel water reprocessing processes, which is a chemical process for recovering uranium and plutonium from irradiated nuclear fuel by a tributyl phosphate extraction method), a plutonium-containing feed liquid in a plutonium purification cycle has high concentration and is possibly subjected to plutonium polymer, so that critical risk exists. Nuclear critical security places special constraints on the structure, shape and size of plutonium-containing feed solution storage tanks. The critical safety of the high-concentration plutonium-containing feed liquid is not sufficiently maintained only by the control of the geometric dimension, and the storage volume is reduced due to the limitation of the dimension, so that the operation efficiency of a factory is influenced, and the input cost of material processing, fluid conveying equipment and troubleshooting is increased. To increase the storage volume, criticality is often controlled using geometric safety devices lined with solid neutron poisons.
Cadmium, gadolinium and boron-containing cement are commonly used as neutron poisons in storage tanks in post-treatment projects in China. Cadmium and gadolinium materials are poor in stability and easy to dissolve or corrode in an acid environment, so that feed liquid is polluted, neutron poison is lost, and a nuclear critical accident can be caused in case of serious conditions; the compression strength of the cement is reduced due to the fact that the boron content in the boron-containing cement is too high, so that the boron content is not more than 5%, the shielding rate per unit volume is low, the specific gravity is large, the tensile strength is relatively low, the weather resistance is poor, and the cement is easy to crack. Moreover, the above materials have relatively low neutron absorption performance, and are not enough to maintain the subcritical state of high-concentration plutonium-containing feed liquid; meanwhile, the specific gravity of the cement is large, the load of a storage tank is increased, the load of a workshop is increased, cadmium and gadolinium have certain toxicity, and the boron-containing cement needs to be poured, filled and molded and does not meet the machining and molding requirements of different shapes.
Disclosure of Invention
The invention aims to solve the technical problem of providing a neutron poison storage tank material for ensuring the critical safety of the storage tank aiming at the defects in the prior art, and also correspondingly provides a preparation method of the neutron poison storage tank material and a neutron poison storage tank made of the neutron poison storage tank material.
The technical scheme adopted for solving the technical problem of the invention is as follows:
the invention provides a neutron poison storage tank material which comprises a main material, wherein the main material comprises the following components in parts by mass:
0.5 to 35 percent of boron carbide, and the balance of polyethylene and polyethylene wax; wherein the mass of the polyethylene wax is 0.5-20% of that of the polyethylene.
Optionally, the boron carbide is nuclear grade boron carbide, or a mixture of nuclear grade boron carbide and non-nuclear grade boron carbide.
Optionally, the beverage also comprises auxiliary materials, wherein the mass of the auxiliary materials is 1-5% of that of the main materials.
Optionally, the adjuvant comprises a coupling agent and an antioxidant.
The invention also provides a preparation method of the neutron poison storage tank material, which is characterized by comprising the following steps:
the main materials are mixed evenly and then are formed into bars or plates.
Optionally, the mixing process of the components in the main material is as follows:
firstly, stirring and premixing polyethylene powder and polyethylene wax, wherein the frequency of a premixed stirring motor is 5-20Hz, the premixing time is 3-10min, and the premixing temperature is 40-90 ℃; after the full premixing, adding boron carbide powder, stirring and mixing, wherein the frequency of a stirring motor for mixing is 5-20Hz, the mixing time is 10-30min, and the mixing temperature is 40-90 ℃.
Optionally, the forming process comprises extrusion, molding and then machining.
Optionally, the extrusion molding process parameters are as follows: the feeding section is 80-210 ℃, the compression section is 180-260 ℃, the homogenization section is 250-320 ℃, the extrusion outlet temperature is 170-200 ℃, the head molding temperature is 230-270 ℃, the extrusion speed is 50-100mm/h, the screw rotating speed is 5-8Hz, and the bar is obtained by air cooling or water cooling after extrusion molding.
Optionally, the process parameters of the die pressing are as follows: and the mould pressing temperature is 180-.
The invention also provides a neutron poison storage tank made of the neutron poison storage tank material or the neutron poison storage tank material prepared by the method.
Optionally, the neutron poison storage tank comprises a storage tank body and a plurality of rods, the rods are fixed in the storage tank body, the storage tank body is formed by the neutron poison storage tank material through die pressing and then machining, and the rods are formed by the neutron poison storage tank material through extrusion forming.
The neutron poison storage tank material is used for preventing chain reaction caused by criticality of high-concentration plutonium in a post-treatment plant in the storage process, and is mainly used for absorbing neutrons and controlling criticality of high-concentration plutonium liquid in the storage tank, so that the environment is harsh, and the performance requirement of neutron absorption is far higher than that of a conventional neutron shielding material. Moreover, because high-concentration plutonium liquid needs to be stored for a long time, the special environment also puts special requirements on the specific gravity, the thermal expansion performance, the rigidity, the tensile strength, the nitric acid corrosion resistance, the thermal aging performance and the irradiation resistance of the storage tank material, and the conventional neutron shielding material can not meet the requirements.
The invention adopts boron carbide, polyethylene and polyethylene wax as main materials of the neutron poison storage tank material, researches show that the neutron poison storage tank material has excellent neutron absorption and critical control performance on high-concentration plutonium liquid in the storage tank, and the material formed by the forming process meets the requirements of the special environment of the neutron poison storage tank on physical and chemical properties, specific gravity, acid corrosion resistance and the like of the material. Particularly, the boron content is high, the hydrogen content is high, the boron content can be adjusted according to use requirements, the slow-release effect on fast neutrons is good, the neutron absorption performance is excellent, particularly, due to the addition of polyethylene wax, the polyethylene wax has high intermiscibility with polyethylene, the fluidity of the material is increased, and boron carbide, the polyethylene wax and polyethylene powder can be fully mixed. And the polyethylene wax can form a coating layer on the surface of the boron carbide in the material mixing process by increasing the discharging temperature, so that the wettability and compatibility of the boron carbide and the polyethylene wax are improved, the moisture adsorbed in the boron carbide powder is removed, the generation of gas in the forming processing process is effectively reduced, and the defects of air holes and the like in a forming material are reduced. Meanwhile, the hydrogen content of the boron-containing polyethylene is not reduced by using polyethylene wax, and the fast neutron moderating performance of the boron-containing polyethylene material is kept. The introduction of polyethylene wax improves the molding processability of the boron-containing polyethylene material and ensures the neutron absorption performance of the material.
In addition, the main material can be formed by mould pressing and mechanical processing or direct extrusion, the formed material has excellent mechanical property and is easy to process and polish. Under the environment of high temperature, high acid and irradiation, the boron content and the hydrogen content of the material prepared by the process are not changed, so that the neutron absorption performance of the material is not changed, and simultaneously, good mechanical properties can be maintained. In addition, compared with the traditional boron-containing cement material, the storage tank has small specific gravity, and the prepared storage tank can obviously reduce the load of plant equipment, effectively increase the volume of the storage tank and reduce the cost of a plant.
Drawings
Fig. 1 is a schematic top view of a neutron poison tank provided in embodiment 3 of the present invention;
fig. 2 is a schematic elevation structure diagram of a neutron poison tank provided in embodiment 3 of the present invention.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it is obvious that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the indication of orientation or positional relationship, such as "on" or the like, is based on the orientation or positional relationship shown in the drawings, and is only for convenience and simplicity of description, and does not indicate or imply that the device or element referred to must be provided with a specific orientation, constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the terms "first" and "second" are used for descriptive purposes only and are not intended to indicate or imply relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood in a specific case to those skilled in the art.
The invention provides a neutron poison storage tank material which comprises a main material, wherein the main material comprises the following components in parts by mass:
0.5 to 35 percent of boron carbide, and the balance of polyethylene and polyethylene wax; wherein the mass of the polyethylene wax is 0.5-20% of that of the polyethylene.
The invention also provides a preparation method of the neutron poison storage tank material, which comprises the following steps:
the main materials are mixed evenly and then formed into bars or plates.
The invention also provides a neutron poison storage tank made of the neutron poison storage tank material or the neutron poison storage tank material prepared by the method.
The extrusion forming process of boron-containing polyethylene rod includes several steps of extrusion, cooling and fixed length cutting. The extrusion adopts a single screw extruder, the temperature of the extruder body is 80-210 ℃ in the feeding section, 180-260 ℃ in the compression section, 250-320 ℃ in the homogenization section, 170-200 ℃ in the extrusion outlet, 230-270 ℃ in the molding temperature of the extruder head, 50-100mm/h in the extrusion speed and 5-8 Hz in the screw rotation speed. The cooling adopts air cooling or water cooling, the cooling speed is matched with the extrusion speed, the size of the diameter of the extruded bar is adjusted and controlled by replacing a machine head, and the length size is adjusted and controlled by cutting at fixed length.
The moulding and machining process for boron-containing polyethylene plate includes the steps of charging, heating and pressurizing, cooling, demoulding and machining. The die can be selected according to requirements, and can be processed into ring plates, upper covers, lower covers and the like of storage tanks with different sizes. The temperature is controlled at 180-250 ℃ and the pressure is controlled at 1000-2500MPa during die pressing. Air cooling is adopted for cooling, and further processing is carried out according to the specific shape required after cooling.
Example 1:
this embodiment provides a neutron poison storage tank panel, including major ingredient and auxiliary material, the major ingredient includes:
74 percent of ultra-high molecular weight polyethylene, 25 percent of nuclear grade boron carbide and 1 percent of polyethylene wax (about 1.4 percent of the mass of the polyethylene)
The auxiliary materials are a coupling agent and an antioxidant, and the addition amount of the coupling agent and the antioxidant is 1 percent of the mass of the polyethylene.
The preparation method of the neutron poison storage tank material comprises the following steps:
(1) mixing material
Mixing materials by adopting a high-speed mixer, firstly premixing auxiliary materials, polyethylene powder and polyethylene wax, wherein the frequency of a stirring motor is controlled at 12Hz, the premixing time is controlled at 5min, and the premixing temperature is controlled at 60 ℃. And adding the nuclear-grade boron carbide powder after full premixing, and mixing, wherein the frequency of a stirring motor is controlled at 12Hz, the mixing time is controlled at 20min, and the mixing temperature is controlled at 60 ℃.
(2) Shaping of
And (3) preparing the boron-containing polyethylene ring plate from the uniformly mixed materials through a die pressing and machining forming process.
The moulding and machining process for boron-containing polyethylene plate includes the steps of charging, heating and pressurizing, cooling, demoulding and machining. The die can be selected according to requirements, and can be processed into ring plates, upper covers, lower covers and the like of storage tanks with different sizes. The temperature during molding is controlled at 210 ℃ and the pressure is 1700 mpa. Air cooling is adopted for cooling, and further processing is carried out according to the specific shape required after cooling.
The detection shows that the boron content of the formed boron-containing polyethylene plate is 24.2 percent, the component uniformity (the difference value between the maximum value and the minimum value of the boron content) is 0.9 percent, and the density is 1.11g/cm3Tensile strength of 16.5MPa and impact strength of 23.1kJ/m2Bending stress of 37.2MPa, Vicat softening point of 132.5 ℃, thermal deformation temperature of 85.6 ℃ and thermal expansion coefficient of 84.6 mu m/m per DEG C at 100 ℃.
Example 2:
the embodiment provides a neutron poison storage tank bar, including major ingredient and auxiliary material, the major ingredient includes the following components of mass fraction:
65% of extrusion grade ultra-high molecular weight polyethylene, 25% of core grade boron carbide and 10% of polyethylene wax (about 15.4% of the polyethylene mass).
The preparation method of the neutron poison storage tank material comprises the following steps:
(1) mixing material
In the embodiment, a high-speed mixer is adopted for mixing materials, firstly, polyethylene powder and polyethylene wax are premixed, during premixing, the frequency of a stirring motor is controlled at 15Hz, the premixing time is controlled at 6min, and the premixing temperature is controlled at 70 ℃. And adding the nuclear-grade boron carbide powder after full premixing, and mixing, wherein the frequency of a stirring motor is controlled at 15Hz, the mixing time is controlled at 25min, and the mixing temperature is controlled at 70 ℃.
(2) Shaping of
After the materials are uniformly mixed, the mixture is directly extruded and molded by a single-screw extruder to prepare the boron-containing polyethylene rod.
In the embodiment, a single-screw extruder is adopted for extrusion molding, the body set temperature during extrusion is 90 ℃, 195 ℃, 245 ℃, 300 ℃, the outlet temperature is 185 ℃ and the head molding temperature is 250 ℃. The extrusion speed is 75mm/h, and the screw rotation speed is 6 Hz. The diameter of the extruded bar is 100mm, air cooling is adopted for cooling, and fixed-length cutting is carried out after cooling.
The detection proves that the boron content of the formed boron-containing polyethylene rod is 24.8 percent, the component uniformity (the difference value between the maximum value and the minimum value of the boron content) is 1.7 percent, and the density is 1.10g/cm3Axial tensile strength of 17.4MPa, radial tensile strength of 17.8MPa, and axial impact strength of 100.97kJ/m2Radial impact Strength 87.03kJ/m2The axial bending stress is 35MPa, the radial bending stress is 34MPa, the Vicat softening point is 127.6 ℃, the axial thermal deformation temperature is 101.1 ℃, the radial thermal deformation temperature is 79.5 ℃, the axial 100 ℃ thermal expansion coefficient is 198.7 mu m/m DEG C, and the radial thermal expansion coefficient is 150.8 mu m/m DEG C.
Example 3
The boron-containing polyethylene rod of example 2 was subjected to an acid corrosion test, a high temperature test, a heat aging test and an irradiation test.
The acid corrosion test result shows that the material has no obvious size and shape change after the bar is corroded in nitric acid with the temperature of 40 ℃ and the concentration of 4mol/L for 180 days, and the hydrogen content and the boron carbide content in the corroded material have no obvious change.
The high-temperature test result shows that the sample piece of the bar is not deformed and has no big end and small end after the high-temperature test at 95 ℃; the appearance, weight, size, tensile strength, boron content and other properties of the material are not obviously changed.
The heat aging test result shows that the size and the weight are not obviously changed before and after the aging test, and the tensile property of the material still has 67.21 percent of the original property after 40 years under the condition of 40 ℃ through test data and deduction.
The irradiation test result shows that the irradiation dose is 5 multiplied by 106Under the Gy condition, the material is crosslinked after irradiation to generate irradiation hardening, the tensile strength is improved by 13.4 percent, the tensile elongation at break is reduced, but the irradiation degradation is not generated.
In addition, through detection, under the four conditions, the boron content, the hydrogen content and other properties have no obvious change, which shows that the material has stable and reliable property for absorbing neutrons and can meet the use requirement of the nuclear critical safety storage tank of a post-treatment plant.
Example 4
As shown in fig. 1 and 2, the present embodiment provides a neutron poison sump including a sump body and a plurality of rods secured in the sump body.
The storage tank body is made of the boron-containing polyethylene ring plate 1 of example 1, and a rod is made of the boron-containing polyethylene rod 2 of example 2, and the rod is formed into the neutron poison storage tank of the present example.
The boron-containing polyethylene section is surrounded by a storage tank outer wall 3, a storage tank inner wall 4 and a tube bundle wall 6 which are made of stainless steel materials and used for protecting neutron poison storage tank materials. The feed liquid 5 is arranged between the tube bundle wall 6 and the inner wall 4 of the storage tank and is simultaneously surrounded by the boron-containing polyethylene ring plates 1 and the boron-containing polyethylene rods 2, and the boron-containing polyethylene rods 2 are uniformly distributed in the storage tank. The polyethylene has high hydrogen content and has good moderation effect on fast neutrons; the boron carbide is uniformly dispersed in the material, and can effectively absorb thermal neutrons. The application can fully absorb neutrons in the feed liquid 5, and a good neutron absorption effect is achieved.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (11)
1. The neutron poison storage tank material is characterized by comprising a main material, wherein the main material comprises the following components in parts by mass:
0.5 to 35 percent of boron carbide and the balance of polyethylene and polyethylene wax; wherein the mass of the polyethylene wax is 0.5-20% of that of the polyethylene.
2. The neutron poison sump material of claim 1, wherein the boron carbide is nuclear grade boron carbide, or a mixture of nuclear grade boron carbide and non-nuclear grade boron carbide.
3. The neutron poison storage tank material according to claim 1 or 2, further comprising an auxiliary material, wherein the mass of the auxiliary material is 1-5% of the mass of the main material.
4. The neutron poison sump material of claim 3, wherein the auxiliary material includes a coupling agent and an antioxidant.
5. A method of preparing the neutron poison sump material of any of claims 1-4, comprising:
the components in the main material are uniformly mixed and then are formed into bars and/or plates.
6. The method for preparing the neutron poison storage tank material according to claim 5, wherein the mixing process of the components in the main material is as follows:
firstly, stirring and premixing polyethylene powder and polyethylene wax, wherein the frequency of a premixed stirring motor is 5-20Hz, the premixing time is 3-10min, and the premixing temperature is 40-90 ℃; after the full premixing, adding boron carbide powder, stirring and mixing, wherein the frequency of a stirring motor for mixing is 5-20Hz, the mixing time is 10-30min, and the mixing temperature is 40-90 ℃.
7. The method of preparing a neutron poison sump material of claim 5,
the bar is formed by extrusion, and the plate is formed by post-die pressing and machining.
8. The method of claim 7, wherein the extrusion process parameters include: the feeding section is 80-210 ℃, the compression section is 180-260 ℃, the homogenization section is 250-320 ℃, the extrusion outlet temperature is 170-200 ℃, the head molding temperature is 230-270 ℃, the extrusion speed is 50-100mm/h, the screw rotating speed is 5-8Hz, and the bar is obtained by air cooling or water cooling after extrusion molding.
9. The method for preparing the neutron poison storage tank material according to claim 7, wherein the process parameters of the die pressing are as follows: and the mould pressing temperature is 180-.
10. A neutron poison reservoir made from the neutron poison reservoir material of any of claims 1-4 or the neutron poison reservoir material made by the method of any of claims 5-9.
11. The neutron poison sump of claim 10, comprising a sump body and a plurality of rods secured in the sump body, the sump body being formed from the neutron poison sump material by post-die machining, the rods being formed from the neutron poison sump material by extrusion.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210230829.5A CN114672086A (en) | 2022-03-10 | 2022-03-10 | Neutron poison storage tank material and preparation method thereof, and neutron poison storage tank |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210230829.5A CN114672086A (en) | 2022-03-10 | 2022-03-10 | Neutron poison storage tank material and preparation method thereof, and neutron poison storage tank |
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| Publication Number | Publication Date |
|---|---|
| CN114672086A true CN114672086A (en) | 2022-06-28 |
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| CN202210230829.5A Pending CN114672086A (en) | 2022-03-10 | 2022-03-10 | Neutron poison storage tank material and preparation method thereof, and neutron poison storage tank |
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN105761773A (en) * | 2016-03-07 | 2016-07-13 | 镇江纽科利核能新材料科技有限公司 | Preparation method for neutron absorption material in storage transportation of spent fuel |
| CN110358177A (en) * | 2019-08-07 | 2019-10-22 | 中国核动力研究设计院 | A kind of Boron-containing-PE stick and its preparation process |
| CN110739093A (en) * | 2019-09-23 | 2020-01-31 | 中国核电工程有限公司 | Critical safety control method for solution storage tank in nuclear fuel post-treatment |
| CN112143066A (en) * | 2019-06-28 | 2020-12-29 | 安徽应流久源核能新材料科技有限公司 | Boron-containing polyethylene composite shielding bar and preparation method thereof |
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Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN105761773A (en) * | 2016-03-07 | 2016-07-13 | 镇江纽科利核能新材料科技有限公司 | Preparation method for neutron absorption material in storage transportation of spent fuel |
| CN112143066A (en) * | 2019-06-28 | 2020-12-29 | 安徽应流久源核能新材料科技有限公司 | Boron-containing polyethylene composite shielding bar and preparation method thereof |
| CN110358177A (en) * | 2019-08-07 | 2019-10-22 | 中国核动力研究设计院 | A kind of Boron-containing-PE stick and its preparation process |
| CN110739093A (en) * | 2019-09-23 | 2020-01-31 | 中国核电工程有限公司 | Critical safety control method for solution storage tank in nuclear fuel post-treatment |
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