RU2606233C2 - Sandwich type structure multilayer material for radiation protection - Google Patents

Abstract

FIELD: manufacturing technology.

SUBSTANCE: invention relates to sandwich type structure multilayer material for radiation protection. Protective material contains layer of scintillation material, during ionizing radiation absorption ensuring conversion of ionizing radiation into plurality of scintillation photons or low energy photons on 1 MeV of ionizing radiation supplied energy and low energy photons uniform radiation in all directions. Material also contains layer for reception and partial attenuation of ionizing radiation, arranged on one side of said scintillation material layer and also intended for low energy photons absorption from scintillation material layer, and layer of material intended for partial attenuation of initial radiation flux and low energy photons absorption from scintillation material layer and located on side of said scintillation material layer, opposite to side, on which ionizing radiation receiving material layer is arranged. At that thickness of ionizing radiation receiving material layer less than thickness of scintillation material layer and is less than or equal to thickness of photons absorbing material layer.

EFFECT: disclosed is material for radiation protection.

19 cl, 6 dwg, 1 tbl

Description

Technical field

The present invention relates to radiation protection, and more particularly to radiation protection material having scintillation properties, such as a sandwich structure, i.e. being a multilayer material.

State of the art

Materials for radiation protection are widely used in medicine during X-ray examination of patients to protect those parts of the patient’s body that should not be exposed to radiation (X-ray) radiation, as well as to protect the doctors who conduct the examination and other patients nearby.

Traditional materials that are used in medicine to protect against radiation typically contain lead or lead oxide. The use of lead is inconvenient due to the fact that lead pollutes the environment due to its toxicity and also has a relatively high specific gravity, which is why medical aprons that are put on the patient and the doctor conducting an X-ray examination, for example, in dentistry or an X-ray examination of internal organs very heavy.

As a radiation absorbing layer, tungsten alloys can also be used, which provide a good alternative to lead. Compared to traditional shielding materials, tungsten alloys show excellent results. These alloys have a high density, therefore, provide the same absorption of X-ray radiation energy as lead, but the amount of material used for protective clothing is 30% less. However, tungsten is a material that is very difficult to process; it has a high melting point and high hardness. The production of alloys requires expensive equipment. All this complicates and increases the cost of manufacturing a protective material.

Currently, there is an acute problem associated with the creation of a material for radiation protection, which would provide the same radiation absorption properties as lead, but would be light and simple to manufacture.

To date, no material has been proposed or used for radiation protection based on materials exhibiting scintillation properties when stimulated by ionizing radiation.

Scintillators are substances that have the ability to emit light when absorbing ionizing radiation, such as gamma rays, electrons, alpha particles, etc. As a rule, the emitted number of photons for a given type of radiation is approximately proportional to the absorbed energy.

The light output is the number of photons emitted by the scintillator when it absorbs a certain amount of energy, usually 1 MeV. A large light output is considered to be 50-70 thousand photons per 1 MeV.

Three mechanisms of the interaction of gamma rays with matter are known.

Photo effect. If the energy of the γ-quantum is greater than the binding energy of the electron shell of the atom, a photoelectric effect occurs. This phenomenon consists in the fact that the photon is completely absorbed by the atom, and one of the electrons in the atomic shell is ejected outside the atom.

The Compton effect is the scattering of gamma quanta by free electrons. An electron can be considered free if the energy of gamma rays is many times higher than the electron binding energy. As a result of the Compton-effect instead of primary photons of energy E _γ appears scattered photon with energy E _'γ <E _γ, and an electron in which the scattering occurred, it acquires kinetic energy.

Formation of an electron – positron pair . A photon interacting with a substance forms an electron-positron pair. The probability of the formation of an electron-positron pair increases with increasing photon energy and with increasing nuclear charge.

The energy absorbed in the scintillator is converted into light, the conversion time is called the time of emission. The time dependence of scintillator emission from the moment of particle absorption (emission curve) can usually be represented as a decreasing exponent. Typical flashing times for inorganic scintillators range from tens of nanoseconds to tens of microseconds.

Inorganic single crystals are most often used as scintillators. However, it is possible to use organic substances, which are also widely known in the art, for example, naphthalene C ₁₀ H ₈ , anthracene C ₁₄ H ₁₀ , transstilbene C ₁₄ H ₁₂ .

NaI, CsI, LiI, ZnS, CdS, BGO (Bi ₄ Ge ₃ O ₁₂ ), Lu _1.8 Y _.2 SiO ₅ : Ce are used as inorganic scintillators. Transparent ceramic scintillators are obtained from transparent ceramic materials based on Al ₂ O ₃ , Y ₂ O ₃ oxides and derivatives of Y ₃ Al ₅ O ₁₂ and YAlO ₃ oxides, as well as MgO, BeO.

Primary fluorescence centers are excited due to energy loss by incident radiation. When these excited states decay, light is emitted in the ultraviolet wavelength range. The absorption length of this ultraviolet, however, is very short: the fluorescence centers are opaque to their own emitted light.

It was found that scintillators can be used to radiation protection, but for this a layer of scintillator material should be surrounded on both sides by at least two layers that serve to absorb radiation, with the formation of a so-called sandwich structure.

SUMMARY OF THE INVENTION

An object of the present invention is to provide a radiation protection material having a sandwich structure and exhibiting scintillation properties when stimulated by ionizing radiation, which would provide the same radiation absorption properties as lead, but would not be toxic, and be lighter than lead , tungsten or other metals, and had a simpler production method than alloys of tungsten.

The problem according to the invention is solved by creating a multilayer material for radiation protection such as a sandwich structure containing

a layer of scintillation material, which, when absorbing ionizing radiation, converts the specified ionizing radiation energy into a set of scintillation or low-energy photons by 1 MeV of the supplied ionizing radiation energy, mainly of the x-ray and gamma-ray energies, and uniform emission of low-energy photons in all directions,

a layer of material for receiving and partial attenuation of ionizing radiation, placed on one side of the specified layer of scintillation material and also designed to absorb low-energy photons from the layer of scintillation material,

a material layer for absorbing low-energy photons from a layer of scintillation material, which also attenuates ionizing radiation, and placed on the side of the specified layer of scintillation material, opposite to the side on which the layer of material for receiving ionizing radiation is placed,

the thickness of the layer of material for receiving ionizing radiation is less than the thickness of the layer of scintillation material and less than or equal to the thickness of the layer of material for the absorption of photons.

According to a second embodiment, the sandwich-type laminate for radiation protection comprises

a plurality of layers of scintillation material, which, when absorbing ionizing radiation, converts the indicated ionizing radiation energy into a plurality of scintillation or low-energy photons per 1 MeV of the supplied ionizing radiation energy, mainly of the X-ray and gamma-ray energies, and uniform emission of low-energy photons in all directions,

a layer of material for receiving and partially attenuating ionizing radiation, placed on one side of the first layer of the specified plurality of layers of scintillation material and also designed to absorb low energy photons from the adjacent layer of scintillation material,

a plurality of layers of material intended for absorbing low-energy photons from scintillation material layers by the number of scintillation material layers, as well as to partially attenuate radiation, and each layer of the plurality of layers is placed on the side of the corresponding scintillation material layer, opposite to the side on which the material layer is placed for receiving ionizing radiation,

wherein the thickness of the layer of material for receiving ionizing radiation is less than the thickness of each of the plurality of layers of scintillation material and less than or equal to the thickness of each of the layers of material for absorbing photons.

Preferably, the thickness of the layer of scintillation material to achieve the effect of 50% attenuation of radiation, which is in the range of 0.001-0.511 MeV, is in the range from 0.01 mm to 26 mm For a wider range of energy values or for a higher percent attenuation, the upper limit of the layer thickness range should be shifted upward.

It is possible that all of these layers of the multilayer material be compressed to form a monolithic layer, or fixed in any other mechanical way (frame, twisting). If conditions allow, the possibility of not fixing the layers is also allowed, which does not affect the weakening ability.

Preferably, the scintillation material layer is formed from a substance selected from the group consisting of NaI, CsI, LiI, ZnS, CdS, BaF ₂ , BGO (chemical formula Bi ₄ Ge ₃ O ₁₂ ), Lu _1.8 Y _.2 SiO ₅ : Ce.

Moreover, it is preferable that the layer of material for receiving ionizing radiation and each layer adjacent to the layer of scintillation material and designed to absorb low-energy photons be formed of a metal or alloy selected from the group consisting of CU, AL, alumina, Fe, steel, W.

Preferably, the thickness of the layer of material for receiving ionizing radiation of not more than 0.511 MeV is in the range from 0.01 mm to 5 mm (for Fe iron) and the thickness of each layer of a plurality of layers of material adjacent to the layer of scintillation material and designed to absorb low-energy photons, also ranges from 0.01 mm to 5 mm (for iron Fe). For higher energies and / or the need to use a metal or alloy from the aforementioned group, the layer thickness will change to a greater extent.

According to the invention, an article is proposed for radiation protection containing a multilayer material such as a sandwich structure.

For ease of use, the product may contain a sealing shell, transparent to ionizing radiation, in which the multilayer material is placed.

Preferably, the product has a shape selected from the group consisting of a plate, ball, cylinder, parallelepiped.

The technical effect achieved is that the proposed radiation protection material having a sandwich structure has a low specific gravity and small thickness, but it provides the same radiation attenuation effect that lead provides, is easy to manufacture compared to tungsten, and does not pollute environment and does not pose a threat to human health, unlike lead, provides a reduction in the cost of special licensing for use. The specified material can be used in medicine for the manufacture of clothing for protection against x-ray radiation, for sheathing the walls of a room where a radiological study is carried out. It can also be used as a collimator. The material based on the sandwich structure can be used in a wide range of devices used primarily in the fields of medicine, industry, nuclear energy and high-energy physics.

The proposed sandwich material can be placed in a shell of a transparent to radiation material for ease of use.

Brief Description of the Drawings

The invention is further explained in the description of the preferred non-limiting embodiments of the invention with reference to the accompanying drawings, in which:

Figure 1 depicts schematically a material for protection against x-ray radiation having a sandwich structure containing three layers, according to the invention;

Figure 2 depicts schematically an X-ray protection material having a sandwich structure comprising a plurality of layers according to a second embodiment of the invention;

Figure 3 depicts an embodiment when the thickness of the layer of material for receiving ionizing radiation is equal to the thickness of the layer of material for absorbing photons, according to the invention;

Figure 4 depicts an embodiment when the layers of material for receiving ionizing radiation of the material, scintillation material and material for absorbing photons have different thicknesses, according to the invention;

Figure 5 depicts a product for protection against x-ray radiation of medical personnel in the form of an apron that protects the operator when conducting x-ray examination, according to the invention;

6 depicts various forms of products for protection against x-ray radiation in the form of a plate, ball, cylinder and parallelepiped.

DESCRIPTION OF PREFERRED EMBODIMENTS

According to the invention, a multilayer material for radiation protection having a sandwich structure is provided.

In the first embodiment, the sandwich-type laminate material 1 (FIG. 1) comprises a scintillation material layer 2, which, when absorbing ionizing radiation γ, converts said ionizing radiation energy into a plurality of scintillation photons or low-energy photons per 1 MeV of supplied ionizing energy radiation predominantly x-ray and gamma-ray energy range and uniform emission of low-energy photons in all directions.

The material 1 also contains a layer 3 for receiving ionizing radiation γ, placed on one side of the scintillation material layer 2 and intended to partially attenuate the initial radiation flux and to absorb low-energy photons from the scintillation material layer 2.

The material 1 also contains a layer 4, designed to absorb low energy photons from a layer 2 of scintillation material and placed on the side of the layer 2 of scintillation material, the opposite side, on which the layer 3 of material for receiving ionizing radiation is placed, which can also contribute to the partial attenuation of the incident ionizing radiation.

The thickness of the material layer 3 for receiving ionizing radiation is less than the thickness of the scintillation material layer 2 and less than or equal to the thickness of the material layer 4 for absorbing photons.

In the second embodiment of the invention, the sandwich-type laminate material 1 (FIG. 2) comprises a plurality of layers 2, 2 ′ of scintillation material (two layers are shown in FIG. 2), which provides, when absorbing ionizing radiation, γ a conversion of said ionizing radiation energy into many scintillation photons or low-energy photons at 1 MeV of the supplied energy of ionizing radiation, and uniform emission of low-energy photons in all directions. This option is possible in cases where it is necessary to reduce the cost of using scintillating substances with a slight increase in metal layers.

Similarly to the first embodiment, the material 1 also contains a layer 3 of material for receiving ionizing radiation, placed on one side of the first layer from the specified set of layers 2, 2 'of scintillation material and intended to partially weaken the initial flux and also to absorb low-energy photons from the adjacent layer 2 scintillation material,

Material 1 also contains a plurality of layers 4, 4 ′ of material intended to partially attenuate the initial flow and also to absorb low energy photons from layers 2, 2 ′ of scintillation material, according to the number of layers of scintillation material, and each layer 4, 4 ′ of this set layers is placed on the side of the corresponding layer 2, 2 'of scintillation material, opposite to the side on which the layer of material for receiving ionizing radiation is placed.

The thickness of the layer 3 of material for receiving ionizing radiation is less than the thickness of each of the plurality of layers 2, 2 ’of scintillation material and less than or equal to the thickness of layer 4, 4’ of material for absorbing photons.

The thickness of a layer of 2 or 2, 2 ’scintillation material is in the range from 0.01 mm to 26 mm for radiation energy less than or equal to 0.511 MeV for cases requiring 50% attenuation.

All of these layers 2, 3, 4 of the multilayer material 1 can be compressed to form a monolithic layer, or simply bonded, and non-bonding of the layers of material between each other is also allowed.

A layer of 2 or 2, 2 'scintillation material is formed from a substance selected from the group consisting of NaI, CsI, LiI, ZnS, CdS, BaF ₂ , BGO (chemical formula Bi ₄ Ge ₃ O ₁₂ ), Lu _1.8 Y _.2 SiO ₅ : Ce.

The layer 3 of material for receiving ionizing radiation is formed of a metal or alloy selected from the group consisting of CU, AL, alumina, Fe, steel, W.

Each layer of a plurality of layers 4, 4 ′ of material adjacent to layers 2, 2 ′ of scintillation material and designed to absorb low energy photons is formed of a metal or alloy selected from the group consisting of CU, AL, alumina, Fe, steel , W.

The thickness of the layer 3 of the material for receiving ionizing radiation γ is in the range from 0.01 mm to 5 mm (for iron Fe), if necessary, 50% attenuation of radiation with energies up to 0.511 MeV. For higher energies and / or the need to use a metal or alloy from the aforementioned group, the layer thickness will change to a greater extent.

The thickness of each layer 4, 4 'of the multiple layers of material adjacent to the layer of scintillation material and intended to partially attenuate the initial radiation flux and absorption of low energy photons is in the range from 0.01 mm to 5 mm (for iron Fe, if necessary, 50% attenuation of radiation with energies up to 0.511 MeV). For higher energies and / or the need to use a metal or alloy from the aforementioned group, the layer thickness will change to a greater extent. Layers 2, 2 ’or 4, 4’ can be of different thicknesses (Figs. 3 and 4).

The invention also provides a radiation protection article comprising a sandwich-type laminate. Figure 5 shows an apron for medical personnel conducting an x-ray examination, divided into many cells, each of which is placed a plate of multilayer material, and the plates overlap each other, while ensuring flexibility of the apron as a whole.

The product may be in the form of a plate, balls or parallelepipeds and may contain a sealing shell that is transparent to ionizing radiation.

Products can be used for wall cladding of rooms in which a radiological examination is carried out, or in industrial technological rooms. This ensures a reduction in the weight of products compared with lead and other metals and alloys, eliminates environmental pollution and harmful effects on human health, and reduces the cost of the product and the manufacturing process.

A multilayer material for radiation protection works as follows.

The ionizing radiation γ passes through layer 3, partially attenuated due to the usual attenuation processes (Fig. 1), and enters layer 2 of scintillation material, which exhibits scintillation when ionizing radiation attenuated by layer 3 is incident on it. Layer 2 of scintillation material provides transformation ionizing radiation into a plurality of scintillation photons or low-energy photons at 1 MeV of the supplied ionizing radiation energy for a wide range of x-ray and gamma radiation, and uniform radiation tones of low energy in all directions. Low-energy photons are transmitted to layers 3 and 4 as secondary radiation, and layers 3 and 4 absorb scintillator re-emitted photons and partially affect the attenuation of the initial gamma-ray flux due to the usual processes of interaction of γ-quanta with the matter of layers 2 and 4, t .e. photoelectric effect, Compton effect and the formation of electron-positron pairs.

Scintillator manufacturing techniques are well known in the art. However, since the only scintillator application known so far is nuclear physics, namely particle detection (tomography devices, etc.), for this application scintillators are mainly made in the form of scintillation matrices. Scintillation matrices are a linear or two-dimensional array of many scintillation pixels separated by optically isolated reflective channels. Depending on the type of scintillation material and its thickness, the active region of scintillation matrices can be made from 5 mm to 200 mm with a single pixel size of up to 0.2 mm. Depending on the application and the scintillator used, it is possible to produce various types of reflectors located between the pixels to minimize crosstalk. The minimum pixel sizes of scintillation matrices are determined mainly by the mechanical properties of crystals, i.e. hardness, plane orientation of the crystal, ease of machining. In nuclear medicine, scintillation matrices can be used in conjunction with position-sensitive photoelectronic multipliers for the manufacture of detectors. Obviously, in this application, the technological process for the production of scintillation matrices, which provides excellent light output and excellent uniformity between pixels, is not only a complex but also a labor-intensive process, which undoubtedly affects the cost of such products. And if for the use in nuclear medicine such a manufacture is justified, then for the proposed invention this is not necessary. The present invention assumes the use of any type of scintillator manufacturing, but without the need for special matrices that increase the cost and complicate the manufacturing process.

A comparative table is presented below, which shows data on the thickness and weight of materials for protection against gamma radiation, necessary to attenuate the initial flux of gamma rays of 0.511 MeV by 90%. Materials used to date include lead (Pb), tungsten (W), iron (Fe), and concrete. According to the invention, scintillation materials such as NaI, CsI, BaF ₂ , Lu _1.8 Y _.2 SiO ₅ : Ce, BGO (chemical formula Bi ₄ Ge ₃ O ₁₂ ), CdWO _{4 are} proposed for use _.

Table Materials (Pb) (W) (Fe) Concrete NaI Csi Baf ₂ Lu _1.8 Y _.2 SiO ₅ : Ce BGO (Bi ₄ Ge ₃ O ₁₂ ) Cdwo ₄ Thickness cm 1,1 1.7 6 24 6.3 5 4.8 2.6 2,3 2.2 Weight, kg 212 192 472 564 237 230 234 187 166 176

The experimental data for Pb, W, Fe and concrete were obtained taking into account the dose factor B _D accumulation. Experimental data for a sandwich-type multilayer material, in which the following materials were used as scintillation materials: NaI, CsI, BaF ₂ , Lu _1.8 Y _.2 SiO ₅ : Ce, BGO (Bi ₄ Ge ₃ O ₁₂ ) and CdWO ₄ were obtained excluding dose factor B _D accumulation. These materials attenuate the flow of ionizing radiation of 0.511 MeV by 90%. To form a sandwich structure, iron Fe was used, i.e. the total thickness of the sandwich structure L consisted of the thickness of the scintillator, and the thickness of the two layers of iron Fe 0.6 mm on each side of the scintillator. Weight is for meter × meter plates with specified thickness L.

Claims (27)

1. A multilayer material for radiation protection such as a sandwich structure, containing a layer of scintillation material, which, when absorbing ionizing radiation, converts the specified ionizing radiation energy into a set of scintillation or low-energy photons by 1 MeV of the supplied ionizing radiation energy, mainly of the x-ray and gamma-ray energies, and uniform emission of low-energy photons in all directions, a layer of material for receiving and partial attenuation of ionizing radiation, placed on one side of the specified layer of scintillation material and also designed to absorb low-energy photons from the layer of scintillation material, a layer of material intended to partially attenuate ionizing radiation and to absorb low energy photons from a layer of scintillation material and placed on the side of the specified layer of scintillation material, opposite to the side on which the layer of material for receiving ionizing radiation is placed, the thickness of the layer of material for receiving ionizing radiation is less than the thickness of the layer of scintillation material and less than or equal to the thickness of the layer of material for the absorption of photons. 2. The multilayer material according to claim 1, characterized in that the layer thickness of the scintillation material is in the range from 0.01 mm to 26 mm for ionizing radiation energies not exceeding 0.511 MeV, and achieving the effect of attenuating ionizing radiation by 45-55%, moreover, the upper limit of the thickness value is shifted upward for a wider range of energy values or for a higher percentage of attenuation. 3. The multilayer material according to claim 1, characterized in that all these layers of the multilayer material are pressed to form a monolithic layer. 4. The multilayer material according to claim 1, characterized in that the scintillation material layer is formed from a substance selected from the group consisting of NaI, CsI, LiI, ZnS, CdS, BaF ₂ , BGO (chemical formula Bi ₄ Ge ₃ O ₁₂ ) , Lu _1.8 Y _.2 SiO ₅ : Ce. 5. The multilayer material according to claim 1, characterized in that the material layer for receiving ionizing radiation is formed of a metal or alloy selected from the group consisting of Cu, Al, alumina, Fe, steel, W. 6. The multilayer material according to claim 1, characterized in that each layer adjacent to the scintillation material layer and designed to absorb low energy photons is formed of a metal or alloy selected from the group consisting of Cu, Al, alumina, Fe, steel, W. 7. The multilayer material according to claim 1, characterized in that the thickness of the layer of material for receiving ionizing radiation is in the range from 0.01 mm to 5 mm for energies of ionizing radiation not exceeding 0.511 MeV, and achieving the effect of attenuation of ionizing radiation by 45- 55% in cases where Fe is used, with the upper limit of the thickness being shifted upward for a wider range of energy values or for a higher percent attenuation. 8. The multilayer material according to claim 1, characterized in that the thickness of each layer of the plurality of layers of material adjacent to the layer of scintillation material and designed to absorb low-energy photons is in the range from 0.01 mm to 5 mm for ionizing radiation energies, not exceeding 0.511 MeV, and achieving the effect of attenuation of ionizing radiation by 45-55%, the upper limit of the thickness being shifted upward for a wider range of energy values or for a higher attenuation percentage. 9. A multilayer material for radiation protection such as a sandwich structure, containing a plurality of layers of scintillation material, which, when absorbing ionizing radiation, converts the indicated ionizing radiation energy into a plurality of scintillation or low-energy photons per 1 MeV of the supplied ionizing radiation energy, mainly of the X-ray and gamma-ray energies, and uniform emission of low-energy photons in all directions, a layer of material for receiving and partially attenuating ionizing radiation, placed on one side of the first layer of the specified plurality of layers of scintillation material and also designed to absorb low energy photons from the adjacent layer of scintillation material, a plurality of layers of material intended to partially attenuate ionizing radiation and to absorb low energy photons from layers of scintillation material, according to the number of layers of scintillation material, and each layer of the specified plurality of layers is placed on the side of the corresponding layer of scintillation material, opposite to the side on which the material layer is placed for receiving ionizing radiation, wherein the thickness of the layer of material for receiving ionizing radiation is less than the thickness of each of the plurality of layers of scintillation material and less than or equal to the thickness of each of the layers of material for absorbing photons. 10. The multilayer material according to claim 9, characterized in that the layer thickness of the scintillation material is in the range from 0.01 mm to 26 mm for ionizing radiation energies not exceeding 0.511 MeV, and achieving the effect of attenuating ionizing radiation by 45-55%, moreover, the upper limit of the thickness value is shifted upward for a wider range of energy values or for a higher percentage of attenuation. 11. The multilayer material according to claim 9, characterized in that all of these layers of the multilayer material are compressed to form a monolithic layer. 12. The multilayer material according to claim 9, characterized in that the scintillation material layer is formed from a substance selected from the group consisting of NaI, CsI, LiI, ZnS, CdS, BaF ₂ , BGO (chemical formula Bi ₄ Ge ₃ O ₁₂ ) , Lu _1.8 Y _.2 SiO ₅ : Ce. 13. The multilayer material according to claim 9, characterized in that the layer of material for receiving ionizing radiation is formed of a metal or alloy selected from the group consisting of Cu, Al, aluminum oxide, Fe, steel, W. 14. The multilayer material according to claim 9, characterized in that each layer adjacent to the scintillation material layer and designed to absorb low energy photons is formed of a metal or alloy selected from the group consisting of Cu, Al, alumina, Fe, steel, W. 15. The multilayer material according to claim 9, characterized in that the thickness of the layer of material for receiving ionizing radiation is in the range from 0.01 mm to 5 mm for energies of ionizing radiation not exceeding 0.511 MeV, and achieving the effect of attenuation of ionizing radiation by 45- 55% in cases where Fe is used, with the upper limit of the thickness being shifted upward for a wider range of energy values or for a higher percent attenuation. 16. The multilayer material according to claim 9, characterized in that the thickness of each layer of the plurality of layers of material adjacent to the layer of scintillation material and designed to absorb low-energy photons is in the range from 0.01 mm to 5 mm for ionizing radiation energies, not exceeding 0.511 MeV, and achieving the effect of attenuation of ionizing radiation by 45-55%, the upper limit of the thickness being shifted upward for a wider range of energy values or for a higher attenuation percentage. 17. A product for radiation protection containing a multilayer material such as a sandwich structure according to any one of claims 1 to 16. 18. The product according to 17, characterized in that it contains a sealing shell, transparent to ionizing radiation, in which the multilayer material is placed. 19. The product according to 17, characterized in that it has a shape selected from the group consisting of a plate, ball, cylinder, parallelepiped.

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