Manufacturing method of transparent high-temperature-resistant neutron gamma-ray radiation shielding plate

Abstract

The invention provides a manufacturing method of a transparent high-temperature-resistant neutron gamma-ray radiation shielding plate. The manufacturing method comprises the steps that according to the preset crystalline phase component requirement, raw materials including S < iO2 >, Gd2O3, Bi2O3, Sn2O3, B2O3 and L < i2O > are blended, the B2O3 is introduced in the form of H2BO3, and the L < i2O > is introduced in the form of L < i2CO3 >; grinding the various raw materials to 80 meshes, and uniformly stirring to form a mixture; the mixture is placed in a graphite crucible, the graphite crucible containing the mixture is placed in a silicon-molybdenum rod resistance furnace to be subjected to heating melting treatment, and the mixture is prepared into molten liquid; rapidly pouring the molten liquid into a stainless steel mold preheated to a second preset temperature, then putting the stainless steel mold into a drying oven to be annealed for 2 hours, and controlling the drying oven to be cooled to the room temperature to form cooled base glass; crushing the basic glass to 200 meshes, and carrying out ball milling to obtain a basic glass powder; 8% of an adhesive is added, and roller type granulation is carried out; and finally, shaping the particles and pressing into the shielding plate. The shielding plate is suitable for working in high-level radioactive places such as a reactor, has good neutron and secondary gamma ray shielding capability, and is a manufacturing method of a protective material with excellent mechanical properties.

Description

Technical Field

[0001] The embodiments of the present application relate to the field of nuclear radiation safety protection technology, and in particular to a method for manufacturing a transparent, high-temperature resistant neutron gamma-ray radiation shielding plate. Background Art

[0002] As we all know, radiation shielding materials are materials used to attenuate radiation generated by nuclear reactor cores and large scientific facilities. For example, among the radiation generated by the reactor, the most harmful are neutrons and gamma rays with strong penetrating power. Neutrons and gamma rays are the main radiation sources. Reactor shielding materials are not only bombarded by high-flux rays for a long time, but also work in prominent places such as high temperature, high heat, high pressure, and high corrosion. Protective materials must meet the dual requirements of nuclear safety and radiation protection, that is, reactor neutron protection shielding materials not only require neutrons to be decelerated and slowed down for absorption, but also effectively attenuate and shield gamma rays generated in secondary reaction processes (such as inelastic scattering gamma, neutron capture gamma, etc.), while withstanding harsh working environments. Not only that, some special radiation scenes also urgently need transparent shielding materials that can provide artificial naked vision or direct observation at specific wavelengths.

[0003] Traditional neutron shielding materials include concrete, water, boron-containing polyethylene, borax, etc. Concrete is a mixture of multiple elements and has a certain shielding effect on neutrons and gamma rays. Water or paraffin contains a lot of hydrogen and is a good neutron moderator, but using water or paraffin as a shielding layer has a great impact on the overall mechanical properties of the structure. Polyethylene has a high hydrogen content and a high neutron moderation ratio, and is currently the most widely used neutron shielding material.

[0004] The main disadvantages of traditional neutron shielding materials include: 1) Concrete. Concrete contains a considerable amount of water, which is generally believed to be able to effectively slow down and absorb neutrons. However, the relationship between the material's shielding performance and structural performance (compression, flexural performance, etc.) is a contradiction. The probability of the standard value of the compressive strength of C30 ordinary concrete used in protective buildings being 30MPa / mm2 is 95%, and the flexural strength is only 2.1-3.2MPa. The reliability of concrete engineering materials is not high. Neutron bombardment of concrete can easily lead to the decomposition of hydrated water components, and the concrete has weak resistance to neutron radiation and poor radiation resistance. 2) Water and paraffin. Water evaporates and vaporizes faster when heated, boiling at 100 degrees; paraffin softens and decomposes when heated, and is not suitable as an engineering material. 3) High-density polyethylene. Polyethylene is not resistant to high temperatures, with a softening temperature of about 110°C, poor radiation resistance, and is restricted in many environments. 4) Borax. Boron has a high cross section for thermal neutrons and has limited effect on slowing down fast neutrons. Boron content in borax is not high. As an engineering material, it is bulky and has low space utilization. 5) None of the above materials are transparent and cannot be observed directly by naked eyes.

[0005] With the development of technology, transparent protective materials have gradually emerged. This transparent protective material mainly refers to inorganic glass or organic polymer materials doped with functional metal particles. It is often used as a neutron / gamma-ray protective material, mainly including two types of inorganic protective glass or organic protective glass. For example, lead glass has been used in the field of gamma-ray protection. Nippon Electric Glass Co., Ltd. has announced a radiation shielding glass with a high lead oxide content that can shield gamma rays with an energy of 0.511MeV. The United States, Europe and other countries or regions use borosilicate glass to solidify high-level radioactive waste. Glass containing boron oxide and boron-containing polyethylene are often used as neutron protection materials.

[0006] Among them, inorganic protective glass refers to a radiation protection product that uses silicate glass powder as a base, is doped with lead oxide, etc., melts the mixture at high temperature and casts it into shape, and cools it to form a glass amorphous phase. The radiation attenuation effect of the product depends on the proportion of functional metal or non-metal material components. A high doping amount can, to a certain extent, increase the unit volume density of functional particles and improve shielding performance, but the various particles introduced will inevitably intertwine and embed into the glass phase structure of the original material, which will not only cause a serious decline in the mechanical processing performance and mechanical properties of the material, but also significantly reduce the transmittance after long-term exposure. Among them, organic protective glass refers to a radiation shielding material formed by grafting functional metal ions with organic polymer materials such as phenolic resin and epoxy resin as a base, with high transmittance and light weight, but organic materials are not resistant to high temperatures (soften and deform when above 200 degrees). At the same time, organic materials are not resistant to high-flux radiation, are easy to decompose, are not suitable for long-term work in the harsh working environment of the reactor, and have high production, processing and use costs. Therefore, traditional neutron protection shielding materials generally have defects such as poor radiation resistance, high temperature resistance or poor machining performance, and non-transparent materials. Summary of the invention

[0007] In a first aspect, an embodiment of the present application provides a method for manufacturing a transparent, high temperature resistant neutron gamma ray radiation shielding plate, comprising the following steps:

[0008] S1: According to the preset crystal phase component requirements, SiO2, Gd2O3, Bi2O3, Sn2O3, B2O3 and Li2O raw materials are mixed;

[0009] S2: Grind the raw materials to 80 mesh and stir them evenly to form a mixture;

[0010] S3: placing the mixture in a graphite crucible, placing the graphite crucible containing the mixture in a silicon-molybdenum rod resistance furnace for heating and melting treatment, heating the mixture to a first preset temperature at a rate of 3-5°C / min in the silicon-molybdenum rod resistance furnace and keeping the temperature for 2 hours, so that the mixture is prepared into a molten liquid;

[0011] S4: the molten liquid is quickly poured into a stainless steel mold preheated to a second preset temperature, and then placed in an oven for annealing for 2 hours and the oven is controlled to cool to room temperature to form a cooled basic glass (i.e., a basic glass body, referred to as basic glass, to achieve annealing to eliminate internal stress of the basic glass)

[0012] S5: crushing the base glass to 200 mesh;

[0013] S6: ball-milling the crushed base glass using a high-energy ball mill to obtain powdered base glass;

[0014] S7: adding 8% of adhesive to the powder of the base glass, and performing roller granulation to obtain particles with a particle size of about 0.1 mm;

[0015] S8: Under high pressure 300MPa / cm 2 The particles are shaped and pressed into plates of preset sizes to form shielding plates.

[0016] Preferably, as an implementable method, after forming the shielding plate, the following manufacturing steps are also included:

[0017] S9: performing differential thermal analysis on the obtained shielding plate, measuring the temperature difference between the substance and the reference through a temperature control program, and obtaining a thermal difference curve; the thermal difference curve is a DTA thermal difference analysis spectrum; determining the optimal conditions for heat treatment of the melt according to the thermal difference curve; the optimal conditions for heat treatment of the melt include an optimal nucleation temperature and nucleation insulation time, an optimal crystallization temperature and crystallization insulation time;

[0018] S10: performing heat treatment according to the optimized conditions for heat treatment of the melt to control the crystallization process, and obtaining a finished microcrystalline glass with high crystallinity and high transparency obtained by heating control output of the optimized conditions for heat treatment of the melt.

[0019] Preferably, as an implementable embodiment, the first preset temperature is 1550° C., the second preset temperature is 600° C., the adhesive is paraffin, and the preset dimensions are 5 cm in length, 5 cm in width, and 1 cm in thickness.

[0020] Preferably, as an implementable embodiment, the main component of the microcrystalline glass material is Ga2O3-SiO3-B2O3 system, which has excellent thermal neutron / gamma ray protection performance.

[0021] Preferably, as an implementable method, the heat treatment process includes precisely heating and controlling the optimal nucleation temperature and nucleation insulation time, the optimal crystallization temperature and crystallization insulation time of the base glass according to the melt heat treatment optimization conditions to ensure the optimization of its crystal structure to obtain the high-crystallization and high-transparency microcrystalline glass product.

[0022] The method provided in the embodiment of the present application has the following beneficial effects:

[0023] The transparent and high-temperature resistant neutron gamma-ray radiation shielding plate obtained by the above-mentioned method has the functions of strong radiation resistance and high temperature resistance, and has the characteristics of transparent materials. Therefore, the present invention provides a transparent and high-temperature resistant neutron gamma-ray radiation shielding plate, which is suitable for working in high-level radioactive places such as reactors. It not only has good neutron and secondary gamma-ray shielding capabilities, but also has a method for manufacturing protective materials with excellent mechanical properties. BRIEF DESCRIPTION OF THE DRAWINGS

[0024] Figure 1 A flow chart of a method for manufacturing a transparent, high temperature resistant neutron gamma ray radiation shielding plate;

[0025] Figure 2 Schematic diagram of the design model for the Monte Carlo simulation;

[0026] Figure 3 It is the neutron and photon energy spectrum of the first preset crystal phase component shield when the neutron source detector is 5 cm away from the shield and the corresponding emission angle is 0°;

[0027] Figure 4 It is a curve diagram of the change of the photon flux with the angle corresponding to the neutron passing through the shielding body when the neutron source detector is 5 cm away from the shielding body;

[0028] Figure 5 It is a curve diagram of the change of the neutron attenuation rate passing through the shielding body with the angle corresponding to the first preset crystal phase component shielding body when the neutron source detector is 5 cm away from the shielding body;

[0029] Figure 6 It is the neutron and photon energy spectrum of the first preset crystal phase component when the neutron source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0030] Figure 7 It is a curve diagram of the change of neutron and photon flux with angle when the neutron source detector is 10 cm away from the shielding body and the shielding body of the first preset crystal phase component passes through the shielding body;

[0031] Figure 8 It is a schematic diagram of a curve showing the variation of the neutron attenuation rate of the first preset crystal phase component shield passing through the shield with the angle when the neutron source detector is 10 cm away from the shield.

[0032] Fig. 9 It is the neutron and photon energy spectrum of the first preset crystal phase component when the neutron source detector is 100 cm away from the shield and the shield exit angle is 0°;

[0033] Fig.10 It is the first preset crystal phase component shield when the neutron source detector is 100 cm away from the shield. The shield is a curve diagram of the neutrons passing through the shield and the photon flux changing with the angle;

[0034] Fig.11 It is the first preset crystal phase component shield when the neutron source detector is 100 cm away from the shield. It is a schematic diagram of the curve of the neutron attenuation rate passing through the shield varying with the angle.

[0035] Fig.12 It is the first preset crystal phase component when the photon source detector is 5 cm away from the shield. The shield is the neutron and photon energy spectrum when the exit angle is 0°;

[0036] Fig.13 It is a curve diagram of the change of the photon flux with the angle of the neutrons passing through the shielding body of the first preset crystal phase component shielding body when the photon source detector is 5 cm away from the shielding body;

[0037] Fig.14 It is a curve diagram of the change of the neutron attenuation rate of the shielding body with the angle of the first preset crystal phase component shielding body when the photon source detector is 5 cm away from the shielding body;

[0038] Fig.15 It is the neutron and photon energy spectrum of the first preset crystal phase component when the photon source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0039] Fig.16 It is the first preset crystal phase component shield when the photon source detector is 10 cm away from the shield. The shield is the neutron passing through the shield, and the schematic diagram of the curve of the photon flux changing with the angle;

[0040] Fig.17 It is the first preset crystal phase component shield when the photon source detector is 10 cm away from the shield. It is a curve schematic diagram of the change of the photon attenuation rate passing through the shield with the angle.

[0041] Fig.18 It is the first preset crystal phase component when the photon source detector is 100cm away from the shield. The shield is the neutron and photon energy spectrum when the emission angle is 0°;

[0042] Fig.19 It is a schematic diagram of the curve of the first preset crystal phase component shield when the photon source detector is 100 cm away from the shield, and the photon flux changes with the angle when the neutron passes through the shield;

[0043] Fig. 20 It is a curve diagram of the change of the attenuation rate of photons passing through the shielding body with the angle of the first preset crystal phase component shielding body when the photon source detector is 100 cm away from the shielding body;

[0044] Fig.21 It is the neutron and photon energy spectrum of the second preset crystal phase component shield when the neutron source detector is 5 cm away from the shield and the corresponding emission angle is 0°;

[0045] Fig. 22 When the neutron source detector is 5 cm away from the shield, the second preset crystal phase component shield is a schematic diagram of a curve of neutrons passing through the shield, and photon flux changes with angle.

[0046] Fig.23 A schematic diagram of a curve showing the variation of the neutron attenuation rate of a second shielding body with a preset crystal phase composition passing through the shielding body with the angle when the neutron source detector is 5 cm away from the shielding body.

[0047] Fig.24 It is the neutron and photon energy spectrum of the second preset crystal phase component when the neutron source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0048] Fig.25 The shield is a second preset crystal phase component when the neutron source detector is 10 cm away from the shield. The shield is a neutron passing through the shield, and the schematic diagram of the curve of the photon flux changing with the angle;

[0049] Fig.26 The second preset crystal phase composition when the neutron source detector is 10 cm away from the shield. The shield is a curve diagram of the neutron attenuation rate of the shield as it changes with the angle.

[0050] Fig. 27 It is the neutron and photon energy spectrum of the second preset crystal phase component when the neutron source detector is 100 cm away from the shield and the shield exit angle is 0°;

[0051] Fig.28 It is a curve diagram of the change of neutron and photon flux with angle when the neutron source detector is 100 cm away from the shielding body and the shielding body of the second preset crystal phase component passes through the shielding body;

[0052] Fig.29 It is a curve diagram showing the change of the photon attenuation rate of the second preset crystal phase component shielding body passing through the neutron source shielding body with the angle when the neutron source detector is 100 cm away from the shielding body;

[0053] Fig.30 It is the second preset crystal phase component shield when the photon source detector is 5cm away from the shield, and the neutron and photon energy spectrum when the exit angle is 0°;

[0054] Fig.31 It is a curve diagram of the change of the photon flux with the angle of the neutrons passing through the shielding body of the second preset crystal phase component shielding body when the photon source detector is 5 cm away from the shielding body;

[0055] Fig.32 It is a curve diagram of the change of the neutron attenuation rate of the second preset crystal phase component shielding body passing through the shielding body with the angle when the photon source detector is 5 cm away from the shielding body;

[0056] Fig.33 It is the neutron and photon energy spectrum of the second preset crystal phase component when the photon source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0057] Fig.34 It is a schematic diagram of the curve of the second preset crystal phase component shield when the photon source detector is 10 cm away from the shield, and the photon flux changes with the angle when the neutron passes through the shield;

[0058] Fig.35 It is the second preset crystal phase component shield when the photon source detector is 10 cm away from the shield. It is a schematic diagram of the curve of the photon attenuation rate passing through the shield varying with the angle.

[0059] Fig.36 It is the second preset crystal phase component when the photon source detector is 100cm away from the shield. The shield is the neutron and photon energy spectrum when the emission angle is 0°;

[0060] Fig.37 It is a schematic diagram of the curve of the second preset crystal phase component shield when the photon source detector is 100 cm away from the shield, and the photon flux changes with the angle when the neutron passes through the shield;

[0061] Fig.38 It is a curve diagram showing the variation of the attenuation rate of photons passing through the shielding body with the angle of the second preset crystal phase component shielding body when the photon source detector is 100 cm away from the shielding body;

[0062] Fig.39 It is the neutron and photon energy spectrum of the third preset crystal phase component shield when the neutron source detector is 5 cm away from the shield and the corresponding emission angle is 0°;

[0063] Fig.40 When the neutron source detector is 5 cm away from the shield, the third preset crystal phase component shield is a curve diagram of the neutrons passing through the shield, and the photon flux changes with the angle.

[0064] Fig.41 A schematic diagram of a curve showing the variation of the neutron attenuation rate of a shielding body with a third preset crystal phase component passing through the shielding body with the angle when the neutron source detector is 5 cm away from the shielding body.

[0065] Fig.42 It is the neutron and photon energy spectrum of the third preset crystal phase component when the neutron source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0066] Fig.43 It is the third preset crystal phase component shield when the neutron source detector is 10 cm away from the shield. The shield is a neutron passing through the shield, and the schematic diagram of the curve of the photon flux changing with the angle;

[0067] Fig.44 It is the third preset crystal phase component when the neutron source detector is 10cm away from the shield. The shield is a curve diagram of the neutron attenuation rate of the shield changing with the angle.

[0068] Fig.45 It is the neutron and photon energy spectrum of the third preset crystal phase component when the neutron source detector is 100 cm away from the shield and the shield exit angle is 0°;

[0069] Fig.46 It is a curve diagram of the change of neutron and photon flux with angle when the neutron source detector is 100 cm away from the shielding body and the third preset crystal phase component shielding body passes through the shielding body;

[0070] Fig.47 It is a curve diagram showing the change of the photon attenuation rate of the third preset crystal phase component shielding body passing through the neutron source shielding body with the angle when the neutron source detector is 100 cm away from the shielding body;

[0071] Fig.48 It is the third preset crystal phase component when the photon source detector is 5 cm away from the shield. The shield is the neutron and photon energy spectrum when the exit angle is 0°;

[0072] Fig.49 It is a curve diagram of the change of the photon flux with the angle of the neutron passing through the shield of the third preset crystal phase component shield when the photon source detector is 5 cm away from the shield;

[0073] Fig.50 It is a curve diagram of the change of the neutron attenuation rate of the third preset crystal phase component shield passing through the shield with the angle when the photon source detector is 5 cm away from the shield;

[0074] Fig.51 It is the neutron and photon energy spectrum of the third preset crystal phase component when the photon source detector is 10 cm away from the shield and the shield exit angle is 0°;

[0075] Fig.52 It is a third preset crystal phase component shield when the photon source detector is 10 cm away from the shield. The shield is a neutron passing through the shield, and the schematic diagram of the curve of the photon flux changing with the angle;

[0076] Fig.53It is the third preset crystal phase component shield when the photon source detector is 10 cm away from the shield. It is a schematic diagram of the curve of the photon attenuation rate passing through the shield varying with the angle.

[0077] Fig.54 It is the third preset crystal phase component when the photon source detector is 100cm away from the shield. The shield is the neutron and photon energy spectrum when the exit angle is 0°;

[0078] Fig.55 It is a schematic diagram of the curve of the third preset crystal phase component shield when the photon source detector is 100 cm away from the shield, and the photon flux changes with the angle when the neutron passes through the shield;

[0079] Fig.56 It is a curve diagram of the change of the attenuation rate of photons passing through the shielding body with the angle of the third preset crystal phase component shielding body when the photon source detector is 100 cm away from the shielding body;

[0080] Fig.57 This is a typical differential thermal analysis (DTA) spectrum of the melt. DETAILED DESCRIPTION

[0081] Figure 1 A flow chart of a transparent, high temperature resistant neutron gamma ray radiation shielding plate and a manufacturing method is provided for the embodiment of the present application, as shown in Figure 1 As shown, the embodiment of the present application provides a method for manufacturing a transparent high temperature resistant neutron gamma ray radiation shielding plate, comprising the following steps:

[0082] S1: According to the preset crystal phase component requirements, SiO2, Gd2O3, Bi2O3, Sn2O3, B2O3 and Li2O raw materials are mixed; in the specific technical scheme, the mixing can also be carried out in the following manner, that is, B2O3 is introduced in the form of H2BO3, and Li2O is introduced in the form of Li2CO3;

[0083] S2: Grind the raw materials to 80 mesh and stir them evenly to form a mixture;

[0084] S3: placing the mixture in a graphite crucible, placing the graphite crucible containing the mixture in a silicon-molybdenum rod resistance furnace for heating and melting treatment, heating the mixture to a first preset temperature at a rate of 3-5°C / min in the silicon-molybdenum rod resistance furnace and keeping the temperature for 2 hours, so that the mixture is prepared into a molten liquid;

[0085] S4: the molten liquid is quickly poured into a stainless steel mold preheated to a second preset temperature, and then placed in an oven for annealing for 2 hours and the oven is controlled to cool to room temperature to form a cooled basic glass (i.e., a basic glass body, referred to as basic glass, to achieve annealing to eliminate internal stress of the basic glass)

[0086] S5: crushing the base glass to 200 mesh;

[0087] S6: ball-milling the crushed base glass using a high-energy ball mill to obtain powdered base glass;

[0088] S7: adding 8% of adhesive to the powder of the base glass, and performing roller granulation to obtain particles with a particle size of about 0.1 mm;

[0089] S8: Under high pressure 300MPa / cm 2 The particles are shaped and pressed into plates of preset sizes to form shielding plates.

[0090] After the shielding plate is formed, the following manufacturing steps are also included: S9: performing differential thermal analysis on the obtained shielding plate, measuring the temperature difference between the substance and the reference through a temperature control program, and obtaining a thermal difference curve; the thermal difference curve is a DTA thermal difference analysis spectrum; determining the optimal conditions for heat treatment of the melt according to the thermal difference curve; the optimal conditions for heat treatment of the melt include an optimal nucleation temperature and nucleation insulation time, an optimal crystallization temperature and crystallization insulation time;

[0091] S10: performing heat treatment according to the optimized conditions for heat treatment of the melt to control the crystallization process, and obtaining a finished microcrystalline glass with high crystallinity and high transparency obtained by heating control output of the optimized conditions for heat treatment of the melt.

[0092] Preferably, as an implementable embodiment, the first preset temperature is 1550° C. The second preset temperature is 600° C. The adhesive is paraffin.

[0093] Preferably, as an implementable embodiment, the preset dimensions are 5 cm in length, 5 cm in width and 1 cm in thickness. The main component of the microcrystalline glass material is Ga2O3-SiO3-B2O3 system, which has excellent thermal neutron / gamma ray protection performance.

[0094] Preferably, as an implementable method, the heat treatment process includes precisely heating and controlling the optimal nucleation temperature and nucleation insulation time, the optimal crystallization temperature and crystallization insulation time of the base glass according to the melt heat treatment optimization conditions to ensure the optimization of its crystal structure to obtain the high-crystallization and high-transparency microcrystalline glass product.

[0095] Embodiment 2

[0096] Embodiment 2 of the present invention provides a transparent high temperature resistant neutron gamma ray radiation shielding plate, comprising the following components:

[0097] A. Silicon dioxide forms the grid structure framework of the system, providing stability to the borosilicate microcrystalline system structure. In order to successfully precipitate gadolinium silicate (crystalline phase Gd2SiO5) with a structure similar to apatite and obtain high crystallinity materials, the molar ratio of silicon to gadolinium atoms in the raw material should be about 1:2.

[0098] B. Gadolinium trioxide, which forms the main crystalline phase with SiO2, also plays the role of network modified ion. On the other hand, the neutron capture cross section of gadolinium is 3.63×10 4 (barn, barn), the energy is 1.0×10 -4 When ∼0.1eV, the capture cross section is 1.0×10 3 ~8.0×10 5 b, about 10 Gadolinium is 60 times that of B and is a good thermal neutron absorbing nuclide. For gamma ray shielding, gadolinium has a better KL absorption limit distribution and is mostly used as a component of lead-free protective materials for gamma ray shielding.

[0099] C. Boron oxide and lithium oxide, Gd2O3 (melting point 2420℃) and SiO2 (melting point 1700℃) are both high melting point substances, and the binary phase of the two melts at about 1550℃. In order to appropriately lower the melting temperature, reduce energy consumption and facilitate the control of reaction conditions, B2O3 and Li2O (Li2O accounts for about 2% by mole) are added to the mixture to play an important role in fluxing. At the same time, 10 The thermal neutron reaction cross section of B (natural abundance is about 20%) is about 3840b, and the secondary particle of the reaction is 7 Li and α particles are easier to protect and are also commonly used thermal neutron absorbing nuclides.

[0100] D. Bismuth trioxide: adding Bi2O3 can increase the number of non-oxygen bridges in the system network, further reduce the melting temperature of the base glass, and play a role in fluxing. 3+ The high polarizability of ions reduces the viscosity of the system, increases the migration rate of ions, reduces and inhibits the glass phase of the system, and promotes the formation and growth of tiny grains; the introduction of high-valent ions can also react with free electrons and holes through the ion valence change process to prevent radiation discoloration and improve radiation resistance. Previous studies have shown that Bi2O3 basically does not change the original crystalline phase in the system and can increase the crystallization tendency of the system. From the perspective of radiation protection, the combination of bismuth and gadolinium improves the KL shell absorption limit of the material, which can enhance the material's ability to protect against gamma rays. It is also a lead-free protective material component for shielding gamma rays.

[0101] E. Tin trioxide, Sn2O3 is a clarifier, which produces gas under high temperature conditions, reduces the gas partial pressure in the molten base glass liquid, promotes the growth of bubbles in the liquid, accelerates the escape of gas from the system, improves the transparency of the base glass, and reduces the bubbles in the system.

[0102] F. Silicon carbide, SiC is a small amount of additive, using the strong deoxidation ability of silicon carbide to balance the number of non-oxygen bridge bonds. At the same time, the bubbles generated when the carbon monoxide produced during the deoxidation reaction is discharged from the system are used to stir the materials and accelerate the reaction speed.

[0103] Specific process formula design: Although the molar number of shielding functional particles contained in the material is the same as that of other protective materials, a dense crystalline phase structure is formed inside the material after the heat treatment process, so the new plate's protection efficiency against X / γ rays is greatly improved.

[0104] (i.e. the first preset crystal phase composition) Component 1: 27.5Gd2O3+27.5SiO2+50B2O3 (mol%); density 4.204g / cm 3 ; (i.e. the second preset crystal phase composition) Component 2: 30Gd2O3+30SiO2+40B2O3 (mol%); Density 4.326g / cm 3 ; (i.e. the third preset crystal phase composition) Component three: 37.5Gd2O3+37.5S iO2+25B2O3 (mol%); Density 4.993g / cm 3 ;

[0105] Monte Carlo simulation: Construct a hollow spherical shield with an inner diameter of 5 cm and an outer diameter of 6 cm (i.e., the thickness of the shield is 1 cm). Isotropic neutron and gamma-ray point sources, where the neutron flux of the point neutron source is 1×10 9 n / cm 2 The initial source energy spectrum includes 1MeV fast neutrons, 100keV medium energy neutrons and 0.0253eV thermal neutrons. The gamma ray source is set at the same position. 60 Co source, energy is 1.25MeV. The source term is located at the geometric center of the model. By recording the different count rates in active and passive mode, the attenuation ratio is calculated to evaluate the shielding protection effect. The shielding body is Ga2O3-SiO3-B2O3 system microcrystalline glass with different formulas. Monte Carlo simulation design model can be found in Figure 2 .

[0106] When light irradiates a material, physical phenomena such as absorption, reflection, scattering, and refraction will occur. Absorption and scattering are the main reasons for the material's devitrification in the visible light wavelength range. Reference Transparent glass-ceramics. Beal lGH. Journal of Materials Science, 1969, 4(4): The analysis results given show that silicate glass-ceramics basically do not absorb visible light [1], which means that effectively reducing scattering is the key factor in determining the transparency of glass-ceramics. The conditions for ensuring the visible light transparency of glass-ceramics are: the size of the precipitated crystal phase is much smaller than the wavelength of visible light (crystal phase influence factor); or the refractive index of the precipitated crystal grains is close to the refractive index of the surrounding material (crystal grain influence factor).

[0107] First, an isotropic neutron point source and photon source are established. The neutron source contains 5% of 1MeV fast neutrons, 30% of 100keV medium energy neutrons and 65% of 0.0253eV thermal neutrons. The photon source is a Cs source with an energy of 662keV. With the source as the center, a spherical shield is established at a radius of 0.5cm, and the thickness of the shield is 1cm. With the x-axis as the axis, a point detector is set up every 30° to simulate the neutron and gamma decay rates at a distance of 5cm, 10cm, and 100cm from the material.

[0108] First, the shielding body of the first preset crystal phase composition is 27.5Gd2O3+27.5SiO2+50B2O3 (mol%);

[0109] 2.1 Neutron Source

[0110] The detector is 5 cm away from the shield:

[0111] Neutrons hit the shield and generate a large number of photons, with energy distribution ranging from 0 to 12 MeV, among which photons with energy of 0.5 to 4 MeV are the most numerous. Figure 3 , Figure 4 as well as Figure 5 As can be seen from the figure, the neutron flux is 6.341E-04cm -2 Around, the photon flux is 3.555E-03cm -2 The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 66.425%. Since a large number of photons are generated by the shielding body, the photon attenuation rate is not calculated.

[0112] See also Figure 3 , Figure 4 as well as Figure 5 , Figure 3-Figure 4 This is a schematic diagram of the detector being 5 cm away from the shield: Figure 3 is the neutron and photon energy spectrum when the emission angle is 0°, Figure 4 It is a schematic diagram of the curve showing the change of neutron and photon flux passing through the shield with angle. Figure 5 Schematic diagram of the curve showing how the neutron decay rate passing through the shield changes with angle. Figure 5 Schematic diagram of the curve showing how the neutron decay rate passing through the shield changes with angle.

[0113] The detector is 10cm away from the shield:

[0114] See also Figure 6 , Figure 7 as well as Figure 8 When the detector is 10 cm away from the neutron source, the detected neutron energy spectrum does not change, with the largest number of photons around 5.5 MeV. The neutron flux and photon flux are about one order of magnitude lower than those detected at 5 cm, and the neutron flux is 2.0245E-04 cm -2 , the photon flux is 1.1345E-03cm -2 Compared with the measured neutron flux without shielding, the neutron attenuation rate is about 66.52%.

[0115] Figure 6 and Figure 7 This is a schematic diagram of the detector being 10 cm away from the shield: Figure 6 is the neutron and photon energy spectrum when the exit angle is 0°; Figure 7 It is a schematic diagram of the curve showing the change of neutron and photon flux passing through the shield with angle. Figure 8 Schematic diagram of the curve showing how the neutron decay rate passing through the shield changes with angle.

[0116] 2.1.3 The detector is 100cm away from the shield

[0117] Compared with the case where the detector is 10cm away from the shield, the neutron and photon energy spectra have not changed, but the neutron and photon flux detected at each angle have decreased by two orders of magnitude. The neutron and photon flux measured at different angles are slightly different. The neutron flux is 2.626E-06cm -2 Around, the photon flux is

[0118] 1.459E-05cm -2 Compared with the measured neutron flux without shielding, the neutron attenuation rate is about 66.68%.

[0119] Fig. 9 and Fig.10 This is a schematic diagram of the detector being 100 cm away from the shield: Fig. 9 is the neutron and photon energy spectrum when the emission angle is 0°; Fig.10It is a schematic diagram of the curve of neutron and photon flux passing through the shield changing with angle; Fig.11 It is a schematic diagram of the curve showing the change of neutron decay rate passing through the shield with angle.

[0120] 2.2 Photon Source

[0121] 2.2.1 When the detector is 5 cm away from the shield, the photon energy spectrum does not change compared to the unshielded state, with the largest number of photons around 0.7 MeV. The photon flux is 1.6675E-03 cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 11.52%.

[0122] Fig.12 and Fig.13 This is a schematic diagram of the detector being 5 cm away from the shield: Fig.12 is the neutron and photon energy spectrum when the emission angle is 0°, Fig.13 It is a schematic diagram of the curve showing the change of neutron and photon flux passing through the shield with angle. Fig.14 Schematic diagram of the curve showing how the neutron decay rate passing through the shield changes with angle.

[0123] 2.2.2 The detector is 10cm away from the shield:

[0124] Compared with the unshielded state, the photon energy spectrum has not changed, with the largest number of photons around 0.7 MeV. The photon flux is 5.323E-04 cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 11.60%.

[0125] Fig.15 and Fig.16 This is a schematic diagram of the detector being 10 cm away from the shield: Fig.15 is the neutron and photon energy spectrum when the emission angle is 0°; Fig.16 It is a schematic diagram of the curve of neutron and photon flux passing through the shield changing with angle; Fig.17 It is a schematic diagram of the curve showing the change of the photon attenuation rate passing through the shield with the angle.

[0126] 2.2.3 The detector is 100cm away from the shield

[0127] Compared with the case where the detector is 10 cm away from the shield, the photon energy spectrum does not change. The photon flux is reduced by 2 orders of magnitude to 6.858E-06cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 11.62%.

[0128] Fig.18 and Fig.19This is a schematic diagram of the detector being 100 cm away from the shield: Fig.18 is the neutron and photon energy spectrum when the emission angle is 0°; Fig.19 It is a schematic diagram of the curve of neutron and photon flux passing through the shield changing with angle; Fig. 20 Schematic diagram of the curve showing the change of photon attenuation rate passing through the shield with angle;

[0129] The second preset crystal phase composition, shielding body is 30Gd2O3+30SiO2+40B2O3 (mol%)

[0130] 3.1 Neutron Source

[0131] 3.1.1 The detector is 5cm away from the shield

[0132] Compared with the unshielded state, the neutron and photon energy spectra have not changed. The number of photons generated by neutrons hitting the shield is the same as when the shielding material is component one. The neutron flux is 6.3870E-04cm -2 Around, the photon flux is 3.65E-03cm -2 The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 66.185%.

[0133] Figure 21-22 This is a schematic diagram of the detector being 5 cm away from the shield: Fig.21 is the neutron and photon energy spectrum when the emission angle is 0°, Fig. 22 It is a schematic diagram of the curve showing the change of neutron and photon flux passing through the shield with angle. Fig.23 Schematic diagram of the curve showing how the neutron decay rate passing through the shield changes with angle.

[0134] 3.1.2 When the detector is 10 cm away from the shield

[0135] Compared with the unshielded state, the neutron and photon energy spectra have not changed. The neutron flux is 2.04E-04cm -2 Around, the photon flux is 1.163E-03cm -2 The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 66.26%.

[0136] Fig.24 and Fig.25 This is a schematic diagram of the detector being 10 cm away from the shield: Fig.24 is the neutron and photon energy spectrum when the exit angle is 0°; Fig.25 It is a schematic diagram of the curve showing the change of neutron and photon flux passing through the shield with angle. Fig.26This is a diagram showing the curve of the neutron decay rate through the shield as it changes with angle.

[0137] 3.1.3 The detector is 100cm away from the shield

[0138] Compared with the unshielded case, the neutron and photon energy spectra did not change. Compared with the case where the distance between the detector and the shield was 10 cm, the neutron and photon flux decreased by 2 orders of magnitude. The neutron flux was 2.645E-06cm -2 Around, the photon flux is 1.495E-05cm -2 about.

[0139] Fig. 27 and Fig.28 This is a schematic diagram of the detector being 100 cm away from the shield: Fig. 27 is the neutron and photon energy spectrum when the emission angle is 0°; Fig.28 It is a schematic diagram of the curve of neutron and photon flux passing through the shield changing with angle; Fig.29 Schematic diagram of the curve showing the change of photon attenuation rate passing through the shield with angle;

[0140] 3.2 Photon Source

[0141] 3.2.1 The detector is 5 cm away from the shield

[0142] Compared with the unshielded state, the photon energy spectrum has not changed. The photon flux is 1.6515E-03cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 12.35%.

[0143] The detector is 5cm away from the shield: Fig.30 The photon energy spectrum when the emission angle is 0°, ( Fig.31 A graph of the photon flux passing through the shield as a function of angle; Fig.32 A graph showing the attenuation rate of photons passing through the shield as a function of angle;

[0144] 3.2.2 The detector is 10 cm away from the shield

[0145] Compared with the unshielded state, the photon energy spectrum has not changed. The photon flux is 5.274E-04cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 12.42%.

[0146] Fig.33 and Fig.34 The detector is 10cm away from the shield: Fig.33 The photon energy spectrum when the emission angle is 0°, Fig.34 is a graph of the photon flux passing through the shield as a function of angle; Fig.35 is a graph of the photon attenuation rate passing through the shield as a function of angle;

[0147] 3.2.3 The detector is 100 cm away from the shield

[0148] Compared with the unshielded state, the photon energy spectrum has not changed. The photon flux is 6.792E-06cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 12.45%.

[0149] Fig.36 and Fig.37 The detector is 100cm away from the shield: Fig.36 The photon energy spectrum when the emission angle is 0°, Fig.37 A graph of the photon flux passing through the shield as a function of angle; Fig.38 is a graph of the photon attenuation rate passing through the shield as a function of angle;

[0150] The third preset crystal phase composition, shielding body is 37.5Gd2O3+37.5SiO2+25B2O3 (mol%)

[0151] 4.1 Neutron Source

[0152] 4.1.1 The detector is 5 cm away from the shield

[0153] Compared with the unshielded case, the neutron and photon energy spectra did not change. The neutron flux was 6.449E-04cm -2 Around, the photon flux is 3.76E-03cm -2 The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 65.85%.

[0154] Fig.39 and Fig.40 The distance between the detector and the shield is 5 cm: Fig.39 Neutron and photon energy spectrum when the exit angle is 0°, Fig.40 A graph showing the variation of neutron and photon fluxes passing through the shield with angle; Fig.41 A graph of the decay rate of neutrons passing through a shield as a function of angle;

[0155] 4.1.2 The detector is 10cm away from the shield

[0156] Compared with the unshielded case, the neutron and photon energy spectra did not change. The neutron flux was 2.06E-04cm -2 Around, the photon flux is 1.198E-03cm -2The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 65.93%.

[0157] Fig.42 and Fig.43 The detector is 10cm away from the shield: Fig.42 Neutron and photon energy spectrum when the exit angle is 0°, Fig.43 A graph showing the variation of neutron and photon fluxes passing through the shield with angle; Fig.44 is a graph of the decay rate of neutrons passing through the shield as a function of angle;

[0158] 4.1.3 The detector is 100cm away from the shield

[0159] Compared with the unshielded case, the neutron and photon energy spectra did not change. The neutron flux was 2.67E-06cm -2 Around, the photon flux is 1.54E-05cm -2 The neutron and photon fluxes measured at different angles are slightly different. Compared with the neutron flux measured without shielding, the neutron attenuation rate is about 66.10%.

[0160] Fig.45 and Fig.46 The detector is 100cm away from the shield: Fig.45 Neutron and photon energy spectrum when the exit angle is 0°, Fig.46 A graph showing the variation of neutron and photon fluxes passing through the shield with angle;

[0161] Fig.47 A graph of the decay rate of neutrons passing through a shield as a function of angle;

[0162] 4.2 Photon Source

[0163] 4.2.1 The detector is 5 cm away from the shield

[0164] Compared with the unshielded state, the photon energy spectrum did not change. The photon flux was about 1.592E-03cm-2. Compared with the photon flux measured when unshielded, the photon attenuation rate was about 15.50%.

[0165] Fig.48 and Fig.49 The detector is 5cm away from the shield: Fig.48 The photon energy spectrum when the emission angle is 0°, Fig.49 A graph of the photon flux passing through the shield as a function of angle; Fig.50 A graph showing the attenuation rate of photons passing through the shield as a function of angle;

[0166] 4.2.2 The detector is 10cm away from the shield

[0167] Compared with the unshielded state, the photon energy spectrum did not change. The photon flux was about 5.083E-03cm-2. Compared with the photon flux measured when unshielded, the photon attenuation rate was about 15.59%.

[0168] Fig.51 and Fig.52 The detector is 10cm away from the shield: Fig.51 The photon energy spectrum when the emission angle is 0°, Fig.52 A graph of the photon flux passing through the shield as a function of angle; Fig.53 A graph showing the attenuation rate of photons passing through the shield as a function of angle;

[0169] 4.2.3 The detector is 100cm away from the shield

[0170] Compared with the unshielded state, the photon energy spectrum has not changed. The photon flux is 6.547E-03cm -2 Compared with the measured photon flux without shielding, the photon attenuation rate is about 15.60%.

[0171] Fig.54 and Fig.55 The detector is 100cm away from the shield; Fig.54 The photon energy spectrum when the emission angle is 0°, Fig.55 A graph of the photon flux passing through the shield as a function of angle; Fig.56 A graph showing the decay rate of photons passing through a shield as a function of angle.

[0172] In general, the embodiment of the present invention uses the Monte Carlo input program mcnp to study the influence of different component ratios of a shield on the neutron and photon shielding performance. The simulation results are as follows. When the shield component is 27.5Gd2O3+27.5SiO2+50B2O3 (mol%): when the distance between the detector and the shield is 5cm, the neutron attenuation rate is 66.425%, and the photon attenuation rate is 11.52%; when the distance between the detector and the shield is 10cm, the neutron attenuation rate is 66.52%, and the photon attenuation rate is 11.60%; when the distance between the detector and the shield is 100cm, the neutron attenuation rate is 66.68%, and the photon attenuation rate is 11.62%.

[0173] When the shielding body composition is 30Gd2O3+30SiO2+40B2O3 (mol%): when the distance between the detector and the shielding body is 5cm, the neutron attenuation rate is 66.185%, and the photon attenuation rate is 12.35%; when the distance between the detector and the shielding body is 10cm, the neutron attenuation rate is 66.26%, and the photon attenuation rate is 12.42%; when the distance between the detector and the shielding body is 100cm, the neutron attenuation rate is 66.45%, and the photon attenuation rate is 12.45%.

[0174] When the shielding body composition is 37.5Gd2O3+37.5SiO2+25B2O3 (mol%): when the distance between the detector and the shielding body is 5cm, the neutron attenuation rate is 65.85%, and the photon attenuation rate is 15.50%; when the distance between the detector and the shielding body is 10cm, the neutron attenuation rate is 65.93%, and the photon attenuation rate is 15.59%; when the distance between the detector and the shielding body is 100cm, the neutron attenuation rate is 66.10%, and the photon attenuation rate is 15.60%.

[0175] The following conclusions can be drawn from the simulation process and results: 1. When shielding neutrons, the thermal neutron components are almost completely shielded. 2. The distance between the shielding body and the detector has little effect on the shielding effect. 3. The shielding effects of the three shielding bodies on neutrons are basically the same, with a neutron attenuation rate of 65.85% to 66.68% and a photon attenuation rate of 12.35% to 15.6%. The shielding effect on photons is best when the shielding body composition is 37.5Gd2O3+37.5S i O2+25B2O3 (mol%), and the shielding effect on neutrons is best when the shielding body composition is 27.5Gd2O3+27.5S i O2+50B2O3 (mol%).

[0176] DTA results, see Fig.57 , differential thermal analysis is used to determine the heat treatment conditions of the melt. Differential thermal analysis is an important material heat treatment analysis method. Through a temperature control program, the temperature difference between a substance and a reference substance is measured to obtain a differential thermal curve. It is widely used to determine the characteristic temperature of a substance during a thermal reaction and the amount of heat absorbed or released, including physical or chemical reactions such as phase change, decomposition, combination, solidification, dehydration, and evaporation. If the differential thermal analysis curve protrudes upward, it means that the measured substance undergoes an exothermic reaction at this temperature. If the curve protrudes downward, it means that an endothermic reaction occurs at this temperature. A typical differential thermal analysis DTA spectrum of a melt can be seen at Fig.57 .

[0177] During the sintering process, nucleation is a phase change process, which requires the absorption of energy to establish a new phase and the parent phase equilibrium interface, which increases the free energy of the system. The nucleation temperature should be determined within the range of the thermal difference curve that protrudes downward. After crystallization, the melt becomes a regular crystal lattice, and its free energy is smaller than that of the irregular amorphous state. This means that when the amorphous state changes to the crystalline state, an exothermic reaction will occur in the melt, and the crystallization temperature can be determined by the upward protruding part of the thermal difference curve. The thermal difference analysis results (thermal difference curve) are used to formulate the optimal conditions for the heat treatment of the melt (optimal nucleation temperature and insulation time, optimal crystallization temperature and insulation time, etc.). The melt is fed into a high-temperature resistance furnace, and after the nucleation and crystallization process, it is finally made into a finished protective sheet.

[0178] Finally, it should be noted that the above embodiments are only used to illustrate the technical solutions of the present application, rather than to limit it. Although the present application has been described in detail with reference to the aforementioned embodiments, those skilled in the art should understand that they can still modify the technical solutions described in the aforementioned embodiments, or make equivalent replacements for some of the technical features therein. However, these modifications or replacements do not deviate the essence of the corresponding technical solutions from the spirit and scope of the technical solutions of the embodiments of the present application.

Claims

1. A method for manufacturing a transparent, high temperature resistant neutron gamma ray radiation shielding plate, characterized in that: include: S1: According to the preset crystal phase component requirements, SiO2, Gd2O3, Bi2O3, Sn2O3, B2O3 and Li2O raw materials are mixed; S2: Grind the raw materials to 80 mesh and stir them evenly to form a mixture; S3: placing the mixture in a graphite crucible, placing the graphite crucible containing the mixture in a silicon-molybdenum rod resistance furnace for heating and melting treatment, heating the mixture to a first preset temperature at a rate of 3-5°C / min in the silicon-molybdenum rod resistance furnace and keeping the temperature for 2 hours, so that the mixture is prepared into a molten liquid; S4: quickly pouring the molten liquid into a stainless steel mold preheated to a second preset temperature, then placing it in an oven for annealing for 2 hours and controlling the oven to cool to room temperature to form a cooled base glass; S5: crushing the base glass to 200 mesh; S6: ball-milling the crushed base glass using a high-energy ball mill to obtain powdered base glass; S7: adding 8% of adhesive to the powder of the base glass, and performing roller granulation to obtain particles with a particle size of about 0.1 mm; S8: Under high pressure 300MPa / cm 2 The particles are shaped and pressed into plates of preset sizes to form shielding plates.

2. The manufacturing method according to claim 1, characterized in that: After the shielding plate is formed, the following manufacturing steps are also included: S9: performing differential thermal analysis on the obtained shielding plate, measuring the temperature difference between the substance and the reference through a temperature control program, and obtaining a thermal difference curve; the thermal difference curve is a DTA thermal difference analysis spectrum; determining the optimal conditions for heat treatment of the melt according to the thermal difference curve; the optimal conditions for heat treatment of the melt include an optimal nucleation temperature and nucleation insulation time, an optimal crystallization temperature and crystallization insulation time; S10: performing heat treatment according to the optimized conditions for heat treatment of the melt to control the crystallization process, and obtaining a finished microcrystalline glass with high crystallinity and high transparency obtained by heating control output of the optimized conditions for heat treatment of the melt.

3. The manufacturing method according to claim 2, characterized in that: The first preset temperature is 1550°C.

4. The manufacturing method according to claim 2, characterized in that: The second preset temperature is 600°C.

5. The manufacturing method according to claim 2, characterized in that: The adhesive is paraffin.

6. The manufacturing method according to claim 2, characterized in that: The preset dimensions are a length dimension of 5 cm, a width dimension of 5 cm and a thickness dimension of 1 cm.

7. The manufacturing method according to claim 1, characterized in that: The main component of the microcrystalline glass material is the Gd2O3-SiO3-B2O3 system, and has excellent thermal neutron / gamma ray protection performance.

8. The manufacturing method according to claim 1, characterized in that: The heat treatment process includes precise heating control of the optimal nucleation temperature and nucleation insulation time, the optimal crystallization temperature and crystallization insulation time of the base glass according to the melt heat treatment optimization conditions to ensure the optimization of its crystal structure to obtain the high-crystallization and high-transparency microcrystalline glass product.

9. The manufacturing method according to claim 1, characterized in that: The DTA thermal differential analysis spectrum has a horizontal axis representing temperature and a vertical axis representing thermal differential value; The thermal differential represents the temperature difference between the sample and the reference.

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