A purifying spray for preventing nuclear radiation and its manufacturing method and application

Abstract

The application discloses a kind of purification spray for preventing nuclear radiation and its manufacturing method and its application in absorbing radioactive elements, radiation or neutron in nuclear radiation pollution environment.The manufacturing method is: bismuth source is dispersed in deionized water, add glycerol;Add arabic gum, glycerol, ultrasonic dissolution, then add anhydrous ethanol, gelatin, ultrasonic stirring and dissolving, after dilution, add boron source, after boron source dissolves, add stabilizer, antibacterial agent and antioxidant, stir uniformly, obtain the purification spray for preventing nuclear radiation.The application can absorb rays and neutron in nuclear pollution environment simultaneously, eliminate nuclear radiation and neutron radiation hazard in nuclear pollution environment.The purification spray for preventing nuclear radiation can wrap radioactive nuclide in nuclear pollution environment after solidification, block radioactive nuclide to continue to release rays and neutron to environment, facilitate subsequent treatment of nuclear pollution waste.

Description

Technical Field

[0001] This invention relates to a purification spray for nuclear radiation protection, its manufacturing method, and its application, belonging to the field of nuclear radiation protection. Background Technology

[0002] In recent years, nuclear medicine isotope imaging and therapy technologies have developed rapidly, and the use of radioactive diagnostic and therapeutic drugs has increased rapidly year by year. The resulting radioactive waste gas, wastewater, and solid waste have become a key focus and challenge for radiation safety and protection supervision. Commonly used radionuclides in nuclear medicine include iodine-131 (I-131), technetium-99 (Tc-99), and fluorine-18 (18-F). Among these, the use of radionuclides for treating thyroid diseases accounts for more than 90% of the total use of radionuclide therapy, and the radionuclides used are almost all I-131. Therefore, I-131 is the largest source of radioactive waste gas generated in nuclear medicine activities. The nucleus of I-131 contains 78 neutrons, four more than the number of neutrons in the nucleus of stable iodine nuclides. I-131 is a β-decay nuclide, emitting β rays (99%) and γ rays (1%). I-131 has a long biological half-life. Patients who ingest it become living sources of radiation, emitting beta and gamma rays that can irradiate those around them. The generation of I-131 radioactive waste gas mainly originates from waste gases produced during the dispensing and oral administration of radioactive drugs, waste gases from patient excrement, clothing, and other solid waste, and waste gases containing radioactive elements exhaled by patients during hospitalization. I-131 exists in the atmosphere in two forms: aerosols and gaseous products. Aerosols are suspensions of I-131 dispersed in the air, consisting mainly of non-volatile iodides and iodates. Gaseous products mainly include elemental iodine, hydrogen iodide, and organic iodine (such as radioactive methyl iodine CH3131I). Current waste gas treatment methods mainly include two processes: aerosol filtration and gaseous product adsorption. However, filtration and gaseous product adsorption methods are only effective against micron-sized aerosol particles and high concentrations of radioactive waste gas, respectively. They are ineffective at removing low concentrations of small-molecule elements such as iodine, hydrogen iodide, and organic iodine scattered in the air. Furthermore, studies have shown that when the concentration of organic pollutants in the environment exceeds 10%, the adsorption efficiency of gaseous product adsorption for radioactive methyl iodine decreases rapidly. In addition, current aerosol filtration and gaseous product adsorption technologies can only adsorb I-131 within filter materials such as filter paper and activated carbon. The radionuclide continues to decay within these materials, releasing harmful substances such as radiation and neutrons into the environment. How to promptly block the pollution of the surrounding environment by radionuclides has become one of the urgent problems to be solved in current nuclear radiation protection products. Currently, lead is commonly used to block and absorb persistent nuclear radiation hazards. However, lead and its compounds are toxic and, once inside the body, can harm multiple systems, including the nervous, hematopoietic, digestive, renal, cardiovascular, and endocrine systems.

[0003] Besides nuclear contamination from the use of radiopharmaceuticals, neutrons produced during the preparation of radioactive isotopes using cyclotrons in hospitals are another major source of radiation contamination. Neutrons have strong penetrating power when passing through matter, posing a greater danger to humans than the same dose of X-rays or gamma rays. Furthermore, the interaction of neutrons with the air in the machine room can produce induced radioactive gases such as nitrogen-13 (N-13), carbon-11 (C-11), oxygen-15 (O-15), and argon-41 (Ar-41), further exacerbating nuclear contamination.

[0004] Developing new, highly efficient purification materials and products for nuclear radiation protection is currently crucial for nuclear radiation protection technology and is an inevitable trend and development direction for the further practical application of nuclear medicine and other nuclear energy technologies. Bismuth's X-ray absorption performance is similar to lead, and it has a strong absorption effect on gamma rays. It has one more outer electron than lead and a larger attenuation coefficient, making it more suitable for radiation protection. my country has the world's largest bismuth reserves, and the development and use of numerous oral bismuth preparations demonstrates the potential of bismuth as a green and safe material for nuclear radiation protection. Boron-10, compared to other neutron absorption shielding materials, has advantages such as a large neutron absorption cross-section, no gamma particle release, water solubility, non-toxicity or low toxicity, low reactivity in air, and weak acid-base properties. Furthermore, the abundance of boron-10 and boron-11 in natural boron is 19.78% and 80.22%, respectively, allowing for the use of high doses of natural boron to replace boron-10 as a neutron protection material. The Liaodong region of my country possesses abundant boron-magnesium iron ore resources. Natural boron exists in minerals in compound form, making it readily available and inexpensive. Therefore, compounds containing bismuth and boron can be used to prepare a protective spray product for nuclear radiation, capable of simultaneously protecting against both nuclear radiation and neutron radiation. This would eliminate the hazards of radiation and neutrons in nuclear-contaminated environments, possessing both high scientific research value and practical significance for controlling nuclear-contaminated environments and protecting the health of personnel in nuclear exposure sites. How to formulate this protective spray product is a key technical challenge that needs to be addressed. Summary of the Invention

[0005] The technical problem to be solved by the present invention is to provide a purification spray for nuclear radiation protection, its manufacturing method and application.

[0006] To address the aforementioned technical problems, this invention provides a purification spray for nuclear radiation protection, which contains boron and bismuth elements.

[0007] Preferably, the boron element is derived from at least one of boric acid, boron-10 acid, and soluble boron-containing pharmaceutical products (e.g., bortezomib, ixazomib, tavaborone, criborone, faborbactam-meropenem).

[0008] More preferably, the boric acid has a mass concentration of 0.1% to 10%.

[0009] Preferably, the bismuth element is derived from at least one of non-toxic or low-toxic inorganic bismuth compounds such as bismuth citrate, potassium bismuth citrate, ammonium bismuth citrate, bismuth aluminate, colloidal pectin bismuth, bismuth subcarbonate, bismuth oxide, bismuth tungstate, and bismuth oxychloride.

[0010] The present invention also provides a method for preparing the above-mentioned purification spray for nuclear radiation protection: a bismuth source is dispersed in deionized water, glycerol is added, and the mixture is stirred to prepare solution A; gum arabic and glycerol are added to solution A, and the mixture is dissolved by ultrasonication; then anhydrous ethanol and gelatin are added, and the mixture is stirred by ultrasonication to obtain solution B; solution B is diluted, a boron source is added, and after the boron source dissolves, a stabilizer, an antibacterial agent, and an antioxidant are added and stirred evenly to obtain the purification spray for nuclear radiation protection.

[0011] Preferably, in solution A, the mass ratio of bismuth element in the bismuth source to water is 1:(5-5000), and the volume ratio of glycerol to water is 1:(1-1000).

[0012] Preferably, in solution B, the mass ratio of gum arabic to water is 1:(1-2000), the volume ratio of glycerol to water is 1:(1-1000), the volume ratio of anhydrous ethanol to water is (0-1):(1-2000), and the mass ratio of gum arabic to gelatin is 1:(0.1-10). Anhydrous ethanol is used to improve dispersibility and reduce the viscosity of the liquid; it can also dissolve the liquid without the addition of anhydrous ethanol.

[0013] Preferably, the dilution factor of solution B is 1 to 1000.

[0014] Preferably, the amount of antioxidant added is 0.01% to 1% by mass.

[0015] The present invention also provides the application of the above-mentioned protective spray for nuclear radiation in absorbing radioactive elements, radiation or neutrons in a nuclear radiation contaminated environment.

[0016] This invention provides a simple, rapid, and highly controllable method for preparing a purification spray for nuclear radiation protection.

[0017] Compared with the prior art, the present invention has the following beneficial effects:

[0018] 1) The purification spray for nuclear radiation protection obtained by the method of the present invention can simultaneously absorb radiation and neutrons in a nuclear-contaminated environment, eliminating the hazards of nuclear radiation and neutron radiation in a nuclear-contaminated environment.

[0019] 2) The radiation protection spray obtained by the method of the present invention can encapsulate radioactive nuclides in the nuclear contaminated environment after solidification, preventing the radioactive nuclides from continuing to release radiation and neutrons into the environment, which facilitates the subsequent treatment of nuclear contaminated waste.

[0020] 3) The preparation method of the present invention does not require special equipment or harsh conditions, the process is simple, highly controllable, and easy to achieve large-scale production, and is practical. Detailed Implementation

[0021] To make the present invention more apparent and understandable, preferred embodiments are described in detail below.

[0022] Example 1

[0023] 1 g of bismuth citrate was dispersed in 20 mL of deionized water and stirred to obtain a bismuth citrate suspension. 5 mL of glycerol and 6 g of gum arabic were added to the suspension and dissolved by ultrasonic stirring. Then, 5 mL of glycerol and 10 mL of anhydrous ethanol were added and stirred until homogeneous. Next, 6 g of gelatin was added and dissolved by ultrasonic stirring. During the dissolution process, 0.1% of an antifoaming agent was added. After the gelatin was completely dissolved, 0.1% by volume of essential oil was added, and the pH was adjusted to 4.5 with hydrochloric acid. The resulting solution was diluted 10 times with deionized water, and 10 g of boric acid was added and stirred until dissolved. Then, 0.1 wt% of tea polyphenols, 0.3 wt% of hydroxycellulose, and 0.3 wt% of an antibacterial agent were added and stirred until homogeneous. The resulting purification spray for nuclear radiation protection was prepared and labeled as Sample 1.

[0024] Example 2

[0025] 1 g of potassium bismuth citrate was dispersed in 10 mL of deionized water and stirred to obtain a solution of potassium bismuth citrate. 5 mL of glycerol and 6 g of gum arabic were added to this solution and dissolved by ultrasonic stirring. Then, 5 mL of glycerol and 10 mL of anhydrous ethanol were added and stirred until homogeneous. Next, 6 g of gelatin was added and dissolved by ultrasonic stirring. During the dissolution process, 0.1% of an antifoaming agent was added. After the gelatin was completely dissolved, 0.1% by volume of essential oil was added, and the pH was adjusted to 4.5 with hydrochloric acid. The resulting solution was diluted 10 times with deionized water, and 10 g of boric acid was added and stirred until dissolved. Then, 0.1 wt% of tea polyphenols, 0.3 wt% of hydroxycellulose, and 0.3 wt% of an antibacterial agent were added and stirred until homogeneous. This prepared the purification spray for nuclear radiation protection and was labeled as Sample 2.

[0026] Example 3

[0027] 1 g of potassium bismuth citrate was dispersed in 10 mL of deionized water and stirred to obtain a solution of potassium bismuth citrate. 2 mL of glycerol and 5 g of gum arabic were added to this solution and dissolved by ultrasonic stirring. Then, 10 mL of anhydrous ethanol was added and stirred until homogeneous. Next, 5 g of gelatin was added and dissolved by ultrasonic stirring. During the dissolution process, 0.1% of an antifoaming agent was added. After the gelatin was completely dissolved, 0.1% by volume of essential oil was added, and the pH was adjusted to 4.5 with hydrochloric acid. The resulting solution was diluted 10 times with deionized water, and 6 g of boric acid was added and stirred until dissolved. Then, 0.1 wt% of tea polyphenols, 0.3 wt% of hydroxycellulose, and 0.3 wt% of an antibacterial agent were added and stirred until homogeneous. This prepared the purification spray for nuclear radiation protection and was labeled as sample 3.

[0028] Example 4

[0029] 1 g of colloidal bismuth pectin was dispersed in 100 mL of deionized water and stirred to obtain a suspension of colloidal bismuth pectin. 2 mL of glycerol and 5 g of gum arabic were added to the suspension and dissolved by ultrasonic stirring. Then, 100 mL of anhydrous ethanol was added and stirred until homogeneous. Next, 5 g of gelatin was added and dissolved by ultrasonic stirring. During the dissolution process, 0.1% of an antifoaming agent was added. After the gelatin was completely dissolved, 0.1% by volume of essential oil was added, and the pH was adjusted to 4.5 with hydrochloric acid. The resulting solution was diluted 10 times with deionized water, and 4 g of boric acid was added and stirred until dissolved. Then, 0.1 wt% of tea polyphenols, 0.3 wt% of hydroxycellulose, and 0.3 wt% of an antibacterial agent were added and stirred until homogeneous. The resulting purification spray for nuclear radiation protection was labeled as sample 4.

[0030] Taking the removal of radioactive methyl iodine from the air as an example, the relevant performance test results of the purification spray for nuclear radiation protection obtained in Examples 1-4 are shown in Table 1.

[0031] Table 1: Performance of the purification spray for nuclear radiation protection in removing radioactive methyl iodine obtained in Examples 1-4

[0032]

[0033] Taking shielding against radioactive neutrons in the air as an example, the test results of the relevant performance of the purification spray for nuclear radiation protection obtained in Examples 1-4 are shown in Table 2.

[0034] Table 2: Neutron radiation shielding performance of the purification spray obtained in Examples 1-4

[0035]

Claims

1. A purification spray for nuclear radiation protection, characterized in that, It contains boron and bismuth; the boron is derived from at least one of boric acid, boron-10 acid, and soluble boron-containing pharmaceuticals; the purification spray is used to remove radioactive methyl iodine or to shield against neutron radiation.

2. The purification spray for nuclear radiation protection as described in claim 1, characterized in that, The mass concentration of the boric acid is 0.1-10%.

3. The purification spray for nuclear radiation protection as described in claim 1, characterized in that, The bismuth element is derived from at least one of bismuth citrate, potassium bismuth citrate, ammonium bismuth citrate, bismuth aluminate, colloidal pectin bismuth, bismuth subcarbonate, bismuth oxide, bismuth tungstate, and bismuth oxychloride.

4. The method for preparing the radiation protection spray according to any one of claims 1-3, characterized in that, Bismuth source is dispersed in deionized water, glycerol is added, and the mixture is stirred to prepare solution A. Gum arabic and glycerol are added to solution A and dissolved by ultrasonication. Then anhydrous ethanol and gelatin are added and dissolved by ultrasonication to obtain solution B. Solution B is diluted and boron source is added. After the boron source dissolves, stabilizer, antibacterial agent and antioxidant are added and stirred evenly to obtain the purification spray for nuclear radiation protection.

5. The manufacturing method as described in claim 4, characterized in that, In solution A, the mass ratio of bismuth to water in the bismuth source is 1:(5~5000), and the volume ratio of glycerol to water is 1:(1~1000).

6. The manufacturing method as described in claim 4, characterized in that, In solution B, the mass ratio of gum arabic to water is 1:(1~2000), the volume ratio of glycerol to water is 1:(1~1000), the volume ratio of anhydrous ethanol to water is (0~1):(1~2000), and the mass ratio of gum arabic to gelatin is 1:(0.1~10).

7. The manufacturing method as described in claim 4, characterized in that, The dilution factor of solution B is 1 to 1000.

8. The manufacturing method as described in claim 4, characterized in that, The amount of antioxidant added is 0.01~1% by mass.

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