CN111943612B - Irradiation-resistant high-temperature-resistant fast neutron shielding material and preparation method thereof - Google Patents
Irradiation-resistant high-temperature-resistant fast neutron shielding material and preparation method thereof Download PDFInfo
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
- C04B28/06—Aluminous cements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/04—Concretes; Other hydraulic hardening materials
- G21F1/042—Concretes combined with other materials dispersed in the carrier
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00862—Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2201/00—Mortars, concrete or artificial stone characterised by specific physical values
- C04B2201/20—Mortars, concrete or artificial stone characterised by specific physical values for the density
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses an irradiation-resistant high-temperature-resistant fast neutron shielding material, which comprises hydrogen-containing inorganic salt and an inorganic nonmetal gel materialAnd boron carbide, wherein the content of the hydrogen-containing inorganic salt is 75-95 percent, the content of the boron carbide is 0.1-5 percent, and the balance is inorganic nonmetal gel material; the density of the irradiation-resistant high-temperature-resistant fast neutron shielding material is 1.8g/cm 3 ‑2.4g/cm 3 Hydrogen density of 0.07g/cm 3 ‑0.09g/cm 3 . The invention also provides a preparation method of the shielding material, and the radiation-resistant high-temperature-resistant fast neutron shielding material is obtained by combining the press forming and the maintenance procedures. The provided shielding material can replace organic shielding materials and be applied to radiation fields with high temperature and high neutron fluence, such as neutron plugs, nuclear reactor main pipeline shielding, spent fuel transportation and storage container shielding and the like.
Description
Technical Field
The invention relates to the technical field of radiation protection and nuclear safety, in particular to an irradiation-resistant high-temperature-resistant fast neutron shielding material and a preparation method thereof.
Background
At present, the neutron shielding mainly adopts materials with high hydrogen and high boron content to carry out shielding materials, the penetration capacity of fast neutrons is strong, the shielding difficulty is high, the materials with high hydrogen content are generally needed to be used for slowing down, and then the materials with high neutron absorption cross section are used for absorbing. The organic material has high hydrogen content, is the first choice of the fast neutron shielding material, and the common organic shielding material comprises a polyethylene-based shielding material, a rubber-based shielding material, an epoxy-based shielding material and the like. However, the use temperature of the organic shielding material is lower, for example, the use temperature of the polyethylene and rubber-based shielding material is not more than 100 ℃, and the use temperature of the epoxy-based shielding material is not more than 160 ℃.
In addition, molecular chains of the organic shielding material are easy to break and age in the irradiation process, and when the accumulated fast neutron fluence of the organic shielding material reaches 10 14 n/cm 2 When the material is aged, the material becomes hard and brittle; when the fast neutron fluence reaches 10 15 n/cm 2 Mechanics of time, materialThe performance is obviously reduced, and the shielding material is continuously pulverized and fails along with the extension of the irradiation time; on the outer side of the reactor pressure vessel, the neutron accumulation flux reaches 10 in the reactor life 19 n/cm 2 Above, the organic shielding material cannot meet the irradiation aging requirement.
Disclosure of Invention
The technical problem to be solved by the invention is as follows: the invention provides a radiation-resistant high-temperature-resistant fast neutron shielding material and a preparation method thereof, which solve the problems of radiation aging and thermal aging of the existing organic shielding material in service.
The invention is realized by the following technical scheme:
the radiation-resistant high-temperature-resistant fast neutron shielding material comprises raw materials including 75-95% of hydrogen-containing inorganic salt, 0.1-5% of boron carbide and the balance of inorganic non-metallic gel material in percentage by mass, wherein the hydrogen-containing inorganic salt, the inorganic non-metallic gel material and the boron carbide are contained in the raw materials; the density of the irradiation-resistant high-temperature-resistant fast neutron shielding material is 1.8g/cm 3 -2.4g/cm 3 Hydrogen density of 0.07g/cm 3 -0.09g/cm 3 。
Currently, two problems exist with commonly used organic shielding materials: 1) And (3) thermal aging: the use temperature of the organic shielding material is lower, such as the use temperature of polyethylene and rubber-based shielding material is not more than 100 ℃, and the use temperature of epoxy-based shielding material is not more than 160 ℃; 2) Neutron irradiation aging: molecular chains of the organic shielding material are easy to break and age in the irradiation process, and when the accumulated fast neutron fluence of the organic shielding material reaches 10 14 n/cm 2 When the material is aged, the material becomes hard and brittle; when the fast neutron fluence reaches 10 15 n/cm 2 In the process, the mechanical property of the material is obviously reduced, and the shielding material is continuously pulverized and fails along with the prolonging of the irradiation time; on the outer side of the reactor pressure vessel, the neutron accumulation flux reaches 10 in the reactor life 19 n/cm 2 Above, organic shieldingThe material cannot meet the irradiation aging requirement.
Based on the technical background, the invention provides a high-efficiency irradiation-resistant fast neutron shielding material which mainly comprises inorganic salt with high hydrogen content and an inorganic binder, and a small amount of boron carbide is added. The fast neutron shielding is firstly moderated by using a material with high hydrogen content (inorganic salt containing hydrogen), then is absorbed by using a shielding material (boron carbide) with a high neutron absorption cross section, and particularly needs to be analyzed according to a neutron energy spectrum. For fast neutron shielding of a reactor, the moderating effect is main, and in the shielding material described in the invention, the mass fraction of inorganic salt with high hydrogen content accounts for more than 75%, and the boron carbide content is 0.1% -5%. The hydrogen density in the finished shielding material is 0.07g/cm 3- 0.09g/cm 3 Density of 1.8g/cm 3 -2.4g/cm 3 Moderate mechanical property and neutron irradiation resistance of 5 multiplied by 10 19 n/cm 2 The composite material is 1000 times higher than organic shielding material, and the maximum use temperature reaches 200 ℃. Compared with the high polymer material, the high polymer material has no thermal aging and radiation aging problems in the use process, and does not release toxic gas. The cost is low, and the production cost of the shielding material disclosed by the invention is far lower than that of lead-boron polyethylene, epoxy resin and other organic shielding materials.
More preferably, the hydrogen-containing inorganic salt is aluminum hydroxide.
Increasing the hydrogen density is one of the targets of developing neutron shielding materials, and many materials have higher hydrogen content, such as organic substances like polyethylene, liquid hydrogen, water, sodium hydroxide, magnesium hydroxide, calcium hydroxide, aluminum hydroxide, zirconium hydride, titanium hydride, and the like. Theoretically, these materials have a good shielding effect when used as a shielding material, and it is common knowledge to improve the neutron shielding performance of the material by increasing the hydrogen density. However, substances having a high hydrogen content are not suitable as a shielding material, and therefore, they are required to be comprehensively considered in view of their chemical properties, production costs, and use environments. As for cement, hydroxide is generally alkaline and is a strong coagulant, ordinary cement and other shielding cement cannot be added with hydroxide powder in a large amount in the construction process, and if sodium hydroxide, calcium hydroxide and other substances are added into the cement, the cement can be quickly solidified within minutes or seconds, so that the materials cannot be normally molded, therefore, the added substances in the cement are screened, and experiments require that the addition of other components cannot influence the service performance of the cement. The aluminum hydroxide provided by the invention is relatively proper in ratio, does not react with cement, is beneficial to later-stage compression molding and is beneficial to obtaining the shielding material with high hydrogen density.
Further preferably, the inorganic non-metallic gel material is CA80 or CA70 aluminate cement.
The invention preferably adopts the inorganic nonmetal gel material as CA80 or CA70 aluminate cement, which has good bonding effect and higher strength after dehydration. The aluminate cement hydrate has strong radiation resistance, and the radiation resistance of the aluminate cement hydrate serving as a bonding component can reach 5 multiplied by 10 19 n/cm 2 Its good irradiation resistance has been demonstrated in shielding concrete for nuclear power plants.
Further preferably, the boron carbide in the raw material is a powder having an average particle diameter of 0.5 μm to 7 μm, and further preferably a powder having an average particle diameter of 3 μm to 7 μm.
The excessive consumption of the boron carbide powder can occupy the content of high-hydrogen components and influence the hydrogen content in the shielding material, thereby influencing the shielding effect of the shielding material on fast neutrons. If the dosage of the boron carbide is too low, the absorption capacity of the moderated neutrons is insufficient, and the shielding effect of the shielding material on fast neutrons is also influenced.
The hardness of the boron carbide powder is higher than that of the steel die, when the steel die is formed, if the particle size of the boron carbide powder is too large, the boron carbide particles can seriously scratch the die, and the smaller the particle size of the boron carbide is, the smaller the damage to the steel die is. However, the particle size of the boron carbide powder should not be too fine, and if the particle size of the boron carbide powder is too fine, the higher the content of impurity phase boron oxide, the higher the boron content in the material, and the smaller the particle size of the boron carbide powder, the higher the price, the more the economic efficiency of the shielding material is affected.
A preparation method of an irradiation-resistant high-temperature-resistant fast neutron shielding material is used for preparing the irradiation-resistant high-temperature-resistant fast neutron shielding material, and the mixed raw materials are subjected to compression molding treatment; and curing the pressed semi-finished product to finally obtain the neutron shielding material.
According to the preparation method of the high-efficiency irradiation-resistant fast neutron shielding material, provided by the invention, the density of the shielding material is improved by a method of pressing and curing combination, the porosity is reduced, the defect of a large-size hole with the diameter of more than 1mm is overcome, the components are uniform, the generation of dose hot spots is avoided, and the shielding efficiency of the shielding material is improved.
The specific preparation method mainly comprises the following steps: weighing, mixing, molding and maintaining.
Further preferably, the press forming includes one or two of steel die forming and isostatic pressing.
There are three methods for press forming of the present invention, namely, a steel die forming method, an isostatic pressing forming method, and a steel die forming and isostatic pressing forming combined method. In the steel die forming, the shielding material is designed into a steel die according to the final size of a product, a shielding block is directly pressed, a flat plate large block can be processed, and the required shielding block is processed by a water jet cutter and a diamond slicer. The shielding block can also be directly prepared by an isostatic pressing method, but the shielding block has irregular appearance and needs to be processed.
More preferably, the shielding material is formed by a steel die and then formed by cold isostatic pressing.
The optimal scheme during molding is that the shielding block is molded by a steel die at first, the density of the shielding block is further improved by isostatic pressing, the shielding block molded by the steel die is neat in appearance, and the shielding block can be prepared in net size as long as the design of the die is proper. The density of the shielding material can be improved by more than 10-20% by cold isostatic pressing treatment, so that the shielding efficiency of the shielding material can be improved, and the thickness of the shielding block can be reduced under the same shielding condition.
More preferably, the molding pressure of the steel mold molding is 10MPa-100MPa.
The pressure of the steel die forming is preferably designed to be 10MPa-100MPa, and if the pressure is too high, the abrasion of the boron carbide powder to the die is large.
More preferably, the isostatic compaction is performed at a compaction pressure of 50MPa to 300MPa.
Further preferably, the maintenance treatment method comprises the steps of clear water maintenance and maintenance treatment in a maintenance box; the curing time is 1 to 7 days.
In the curing step, the shielding material may be cured in clear water or in a curing box. According to the actual situation, baking treatment is carried out after clean water maintenance or maintenance box maintenance is finished, the baking temperature is 100-120 ℃, and the baking time is 0.5-3 days.
Further preferably, the method for mixing the raw materials weighed according to the mixture ratio before the compression molding treatment comprises the following steps: dry mixing the materials, and wet mixing; in the wet mixing treatment, the water addition amount is 3-15% of the total mass of the raw materials.
In the mixing process, the mixing amount of water is 3-15% of the total mass of the raw materials, so that the surface of the powder is moist and the powder can be formed.
The invention has the following advantages and beneficial effects:
the high-efficiency radiation-resistant fast neutron shielding material comprises 75-95% of inorganic salt containing hydrogen and 0.1-5% of boron carbide, and the prepared shielding material has hydrogen density as high as 0.07g/cm 3 -0.09g/cm 3 The fast neutron shielding performance is slightly superior to that of lead-boron polyethylene, and the density of the material after being dried is 1.8g/cm 3 -2.4g/cm 3 The shielding material is suitable for fast neutron shielding and has the following beneficial effects:
1. the mechanical property is moderate: the flexural strength of the shielding material is higher than 3MPa, and the compressive strength is higher than 15MPa.
2. Irradiation aging resistance: the neutron irradiation resistance reaches 5 multiplied by 10 19 n/cm 2 Is more than 1000 times higher than that of the organic shielding material,
3. high temperature aging resistance: the maximum service temperature reaches 200 ℃.
Compared with high polymer materials, the high polymer material has no thermal aging and radiation aging problems in the use process, and does not release toxic gas. The production cost of the shielding material provided by the invention is far lower than that of lead boron polyethylene, epoxy resin and other organic shielding materials. Compared with the pouring process of shielding concrete and other shielding materials, the pressing process improves the density of the shielding material, eliminates the defect that the density of the shielding material reaches more than 85-95% after internal pores are dried, has low porosity, no large-size pores with the diameter of more than 1mm, has uniform components, avoids the generation of dose hot spots, and improves the shielding efficiency of the shielding material in unit volume.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not used as limitations of the present invention.
Example 1
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: 10 parts of CA80 aluminate cement, 89 parts of aluminum hydroxide powder and 1 part of boron carbide powder with the average grain diameter of 3 mu m.
Mixing materials: all weighed raw materials are dry-mixed for 2min in a mortar stirrer, 10 parts of water is added, and wet mixing is carried out for 2min.
And (3) pressing and forming: pouring the mixed material into a steel die, wherein the molding pressure is 10MPa; and (5) after demolding, carrying out cold isostatic pressing treatment at the molding pressure of 300MPa, and finally obtaining the shielding block.
And (5) maintenance: and then placing the shielding block into a curing box for curing for 3 days, then placing the shielding block into an oven, wherein the baking temperature is 110 ℃, the baking time is 24 hours, and removing free water in the shielding block.
The density of the shielding material finally prepared is 2.4g/cm 3 Hydrogen density of 0.09g/cm 3 。
Example 2
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: 5 parts of CA70 aluminate cement, 94 parts of aluminum hydroxide powder and 1 part of boron carbide powder with the average grain diameter of 3 mu m.
Mixing materials: all weighed raw materials are mixed in a mortar stirrer for 2min in a dry mode, 3 parts of water is added, and the mixture is mixed for 2min in a wet mode.
And (3) pressing and forming: pouring the mixed material into a steel die, wherein the molding pressure is 10MPa; and (5) after demolding, carrying out cold isostatic pressing treatment at the forming pressure of 250MPa to finally obtain the shielding block.
And (3) maintenance: and then placing the shielding block into a curing box for curing for 3 days, then placing the shielding block into an oven, and curing at the temperature of 110 ℃ for 24 hours to remove free water in the shielding block.
The density of the shielding material finally prepared is 2.3g/cm 3 Hydrogen density of 0.09g/cm 3 。
Example 3
The embodiment provides a high-temperature-resistant irradiation-resistant fast neutron shielding material, which is prepared by the following preparation method:
weighing: according to the weight portion, 15 portions of CA80 aluminate cement, 80 portions of aluminium hydroxide powder and 5 portions of boron carbide powder whose average grain size is 3 micrometers.
Mixing materials: all the weighed raw materials are dry-mixed for 2min in a mortar stirrer, 15 parts of water is added, and the wet mixing is carried out for 2min.
And (3) compression molding: and pouring the mixed material into a steel die, and obtaining the shielding block, wherein the molding pressure is 100MPa.
And (5) maintenance: and then placing the shielding block into a curing box for curing for 7 days, and then placing the shielding block into an oven, wherein the baking temperature is 110 ℃, the baking time is 24 hours, and the free water in the shielding block is removed.
The density of the shielding material finally prepared is 1.8g/cm 3 Hydrogen density of 0.07g/cm 3 。
Example 4
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: 10 parts of CA80 aluminate cement, 89 parts of aluminum hydroxide powder and 1 part of boron carbide powder with the average grain diameter of 3 mu m.
Mixing materials: all weighed raw materials are mixed in a mortar stirrer for 2min in a dry mode, 5 parts of water is added, and the mixture is mixed for 1min in a wet mode.
And (3) pressing and forming: pouring the mixed material into a steel die, wherein the molding pressure is 50MPa; and (5) after demolding, carrying out cold isostatic pressing treatment at the forming pressure of 200MPa to finally obtain the shielding block.
And (5) maintenance: and then placing the shielding block into a curing box for curing for 3 days, then placing the shielding block into an oven, and curing at the temperature of 110 ℃ for 24 hours to remove free water in the shielding block.
The density of the shielding material finally prepared is 2.2g/cm 3 Hydrogen density of 0.085g/cm 3 。
Example 5
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: 10 parts of CA80 aluminate cement, 89 parts of aluminum hydroxide powder and 1 part of boron carbide powder with the average grain diameter of 3 mu m.
Mixing materials: all the weighed raw materials are dry-mixed for 2min in a mortar stirrer, 10 parts of water is added, and the wet mixing is carried out for 2min.
And (3) pressing and forming: and pouring the mixed material into an isostatic pressing die for cold isostatic pressing treatment, wherein the forming pressure is 250MPa.
And (5) maintenance: and then placing the shielding block into clear water for curing for 3 days, then placing the shielding block into an oven, and baking at the temperature of 110 ℃ for 24 hours to remove free water in the shielding block.
The density of the shielding material finally prepared is 2.3g/cm 3 Hydrogen density of 0.081g/cm 3 。
Example 6
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: 10 portions of CA80 aluminate cement, 89.9 portions of aluminum hydroxide powder and 0.1 portion of boron carbide powder with the average grain diameter of 7 mu m.
Mixing materials: all weighed raw materials are dry-mixed for 2min in a mortar stirrer, 10 parts of water is added, and wet mixing is carried out for 2min.
And (3) pressing and forming: pouring the mixture into a steel die with the molding pressure of 10MPa, demolding, and carrying out cold isostatic pressing treatment with the molding pressure of 250MPa to finally obtain the shielding block.
And (3) maintenance: and then placing the shielding block into a curing box for curing for 3 days, then placing the shielding block into an oven, and curing at the temperature of 110 ℃ for 24 hours to remove free water in the shielding block.
The density of the shielding material finally prepared is 2.3g/cm 3 Hydrogen density of 0.08g/cm 3 。
Example 7
The embodiment provides a high-temperature-resistant and irradiation-resistant fast neutron shielding material, which is obtained by the following preparation method:
weighing: calculated by weight portion, 20 portions of CA80 aluminate cement, 75 portions of aluminum hydroxide powder and 5 portions of boron carbide powder with average grain diameter of 3 micrometers.
Mixing materials: all the weighed raw materials are dry-mixed for 2min in a mortar stirrer, 10 parts of water is added, and the wet mixing is carried out for 2min.
And (3) pressing and forming: pouring the mixture into a steel die with the molding pressure of 10MPa, demolding, and carrying out cold isostatic pressing treatment with the molding pressure of 50MPa to finally obtain the shielding block.
And (5) maintenance: and then placing the shielding block into a curing box for curing for 1 day.
The density of the shielding material finally prepared is 2.0g/cm 3 Hydrogen density of 0.078g/cm 3 。
The method for testing the performance of the shielding material comprises the following steps:
1. the density detection method comprises the following steps: and pressing the shielding material with a regular shape by using a mold, maintaining and drying the shielding material, measuring the size of the sample by using a vernier caliper, calculating the volume of the sample, measuring the mass of the shielding block by using a balance with the precision superior to 1mg, and calculating the density of the shielding block according to the mass and the volume of the shielding block.
2. The detection method of the hydrogen density of the shielding material comprises the following steps: firstly preparing a sample with the diameter of 20mm and the height of 20mm, baking for 24h at 160 ℃, removing free water, measuring the size of the sample by using a vernier caliper, measuring the mass of a shielding block by using a balance with the precision superior to 0.1mg, calculating the volume and the initial density of the sample, putting the sample into a muffle furnace, heating to 800 ℃, preserving the temperature for 1h, completely discharging bound water from the sample, weighing the weight of the sample by using a balance after the sample is cooled, calculating the water loss of the sample, and calculating the hydrogen density in the shielding material according to the water loss, the volume and the hydrogen content of the water of the sample.
3. The method for detecting the mechanical property of the shielding block comprises the following steps: processing a mould with the inner cavity size of 40mm multiplied by 160mm, preparing 3 pieces of mechanical property testing standard test blocks with regular shapes for each formula, and testing the flexural strength and the compressive strength of the shielding material by using a mortar flexural tester according to the GBT17671-1999 cement mortar strength testing method. The mechanical properties of the shielding block increased with the cement content, the flexural strength was 3MPa and the compressive strength was 12MPa when the cement content was 5% (shielding material of example 2), and the flexural strength was 8MPa and the compressive strength was 60MPa when the cement content was 20% (shielding material of example 7).
4. The method for testing the shielding performance of the shielding material comprises the following steps: processing a mould with the diameter of 54mm to prepare a shielding block with the diameter of about 54mm and the thickness of 10mm, taking out a lead-boron polyethylene sample with the same size from the lead-boron polyethylene sample, respectively testing the shielding rate of the sample on fast neutrons aiming at the Am-Be fast neutron source, and comparing the shielding rates, wherein the result shows that when the content of aluminum hydroxide is 75% (the shielding material of the embodiment 7), the density is 1.8g/cm 3 When the neutron shielding performance of the shielding material is the same as that of the lead-boron polyethylene, the shielding rate is 24 percent, and when the content of the aluminum hydroxide is close to 90 percent (the shielding material prepared in the embodiment 6), the density is 2.2g/cm 3 In time, the neutron shielding performance of the shielding material is superior to that of lead-boron polyethylene, and the fast neutron shielding rate reaches 27%.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (5)
1. A preparation method of an irradiation-resistant high-temperature-resistant fast neutron shielding material is used for preparing the irradiation-resistant high-temperature-resistant fast neutron shielding material, and the mixed raw materials are subjected to compression molding treatment; curing the pressed semi-finished product to finally obtain the neutron shielding material;
the maintenance treatment method comprises the steps of clear water maintenance and maintenance treatment in a maintenance box; the curing time is 1 to 7 days;
before the compression molding treatment, the method for mixing the raw materials weighed according to the mixture ratio comprises the following steps: dry mixing the materials, and wet mixing; in the wet mixing treatment, the water addition amount is 3-15% of the total mass of the raw materials;
the radiation-resistant high-temperature-resistant fast neutron shielding material comprises raw materials including 75-95% of hydrogen-containing inorganic salt, 0.1-5% of boron carbide and the balance of inorganic non-metallic gel material in percentage by mass, wherein the hydrogen-containing inorganic salt, the inorganic non-metallic gel material and the boron carbide are contained in the raw materials;
the density of the irradiation-resistant high-temperature-resistant fast neutron shielding material is 1.8g/cm 3 -2.4g/cm 3 Hydrogen density of 0.07g/cm 3 -0.09g/cm 3 ；
The hydrogen-containing inorganic salt is aluminum hydroxide;
the boron carbide adopts powder, and the average grain diameter of the powder is 0.5-7 μm;
the inorganic non-metal gel material is CA80 or CA70 aluminate cement.
2. The method for preparing the irradiation-resistant high-temperature-resistant fast neutron shielding material according to claim 1, wherein the press forming comprises one or two of steel die forming and isostatic pressing forming.
3. The method for preparing the radiation-resistant high-temperature-resistant fast neutron shielding material according to claim 2, wherein the shielding material is formed by steel die molding and then is formed by cold isostatic pressing.
4. The preparation method of the radiation-resistant high-temperature-resistant fast neutron shielding material according to claim 2, wherein the molding pressure of the steel mold molding is 10MPa-100MPa.
5. The preparation method of the irradiation-resistant high-temperature-resistant fast neutron shielding material according to claim 2, wherein the isostatic compaction is performed at a compaction pressure of 50MPa to 300MPa.
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