Method of producing nanostructured target for production of molybdenum-99 radioisotope

FIELD: physics.

SUBSTANCE: invention relates to reactor technology of producing molybdenum-99 radioisotope (99Mo), which serves a base for creation of radioisotope technetium-99m generators (99mTc). This method includes production of molybdenum-99 radioisotope at reaction 98Mo(n,γ)99Mo, carried out in a stream of slow neutron nuclear reactor and is carried out using a matrix-buffer of mesoporous inorganic materials, which channels are supplied with molybdenum compounds. Production of target is carried out by impregnation of activated carbon with specific surface area more than 300 m2/g of ammonium paramolybdate solution (NH4)6Mo7O24 and subsequent heat treatment, as a result, on the surface of the channels nano-layers MoO3 are formed. Fraction of recoil atoms 99Mo, leaving layers MoO3 and localized in the buffer depends on thickness of applied layers. Average thickness of nanolayers MoO3 applied in series into channels is set by number of applications and is limited by the effective diameter of channels. After irradiation the separation of core recoil containing activated carbon and starter nanoparticles MoO3 is achieved by elution of more than 97% MoO3 from the target 20% solution of water ammonia. Following the process of extracting cores recoil of a matrix is implemented by gasification of coal component of the matrix by combustion.

EFFECT: technical result provides simple method of making the target, higher efficiency of producing 99Mo due to creation of nano-layers over the entire volume of the matrix, which enables to achieve high homogeneity of “nanolayer-Mo - buffer”, providing efficient use of the starting material and increases efficiency of collecting recoil atoms, obtaining a uniform distribution of molybdenum in the volume of activated carbon during precipitation of molybdenum coating on surface of its mesopores.

3 cl, 1 ex

 



 

Same patents:

FIELD: chemistry.

SUBSTANCE: method of obtaining radioisotope 99Mo includes the irradiation of a target by a beam of neutrons with the following extraction of the target radioisotope, formed as a result of a 98Mo(n,γ)99Mo reaction. As the target applied are nanoparticles of metallic molybdenum or its compounds, insoluble in water, or a water solution of alkali, or water NH4OH solution. Irradiation of the target is carried out in water, or water alkali solution, or water NH4OH solution. The target radioisotope 99Mo is separated in the composition of an anion of water-soluble molybdate(99MoO4)-2 from nanoparticles.

EFFECT: increase of the specific activity of 99Mo radioisotope.

FIELD: physics.

SUBSTANCE: in the disclosed method of obtaining a 228Th radionuclide, which involves irradiating a target, the target material is a natural thorium isotope - 230Th, the target is placed in a linear electron accelerator and irradiated with γ-quanta of deceleration radiation, and the desired 228Th radionuclide accumulates therein during the threshold nuclear reaction 230Th(γ,2n)228Th. The target material can be 230ThF4 or 230ThO2 or 230Th metal.

EFFECT: obtaining α-radiating nuclides, which enables to eliminate shortage of therapeutic α-radiators on the market of medical radionuclides and satisfy increasing demand in the future.

2 cl

FIELD: power industry.

SUBSTANCE: as a target, proposed method uses structured material consisting of molybdenum nanoparticles or its compounds enveloped with a buffer in the form of a solid substance soluble in water or other solvents; at that, d - typical size of nanoparticles is chosen from condition λ/d>>1, where λ - distance of travel in the substance of a nanoparticle of recoil atoms 99Mo. As a result of 99Mo(n,γ)99Mo reaction, recoil atoms are formed, some part of which leaves nanoparticles due to its kinetic energy and is implanted into the buffer enveloping the buffer. After exposure to radiation the target is removed from the reactor, nanoparticles and the buffer is separated with one of known methods. The buffer is supplied for radiochemical processing for separation of a target radioisotope, and molybdenum nanoparticles are returned to the reactor active zone as a part of a new target.

EFFECT: reduction of quantities of radioactive wastes and improvement of use efficiency of fissile material.

6 cl, 1 dwg

FIELD: power engineering.

SUBSTANCE: method to produce a radionuclide bismuth-212 from a nitrate solution containing a mixture of radionuclides thorium-228, thorium-229 and their daughter products of decay, and release of the finished product at an ion-exchange column with cationite. The nitrate solution contains a mixture of radionuclides thorium-228 and thorium-229 and their daughter products of decay, is mixed with ethyl alcohol, this mixture is eluted via the ion exchange column with cationite, where all cations contained in the mixture are absorbed, and as bismuth-212 is accumulated, bismuth-212 is washed by diluted hydrochloric acid.

EFFECT: simplified technological process of production of a radionuclide bismuth-212.

3 cl

FIELD: power industry.

SUBSTANCE: solution containing radionuclides thorium-229, thorium-228 and daughter decay products of these radionuclides is bubbled with gas, thus extracting from them one of daughter radionuclides of thorium-228 - gaseous radon-220. Gas is supplied through aerosol filter to sorption device, and cleaned solution containing mixture of radionuclides thorium-228, thorium-229, as well as daughter decay products of these radionuclides are supplied to radiochemical processing by means ion-exchange resins in order to obtain target radionuclide bismuth-213. As bubbling gas there used is air and/or helium and/or argon and/or krypton and/or xenon. As sorption device there used is hollow volume the dimensions of which provide the residence time of radon-220, which is sufficient for its complete decay to stable radionuclide lead-208, or trap with activated carbon.

EFFECT: reducing the radiation dose intensity in the work area.

4 cl

FIELD: power industry.

SUBSTANCE: solution containing mixture of radionuclides thorium-228 and thorium-229, as well as daughter decay products of these radionuclides is bubbled with gas, thus extracting from them one of daughter decay products of thorium-228 - gaseous radionuclide radon-220. Gas is supplied through aerosol filter to sorption device where as a result of radioactive decay as per chain 220Rn→216Po→212Pb there accumulated is radionuclide lead-212, which, after attainment of saturation of activity of lead-212, is desorbed. The obtained solution is supplied to column with ion-exchange resin from which the daughter decay product of radionuclide bismuth-212 is washed from time to time. As bubbling gas there used is air and/or nitrogen and/or helium and/or argon and/or krypton and/or xenon. As sorption device there used is hollow volume the dimensions of which provide the residence time of radon-220, which is sufficient for its complete decay to radionuclide lead-212, or trap with activated carbon.

EFFECT: reducing the labour intensity of the process and the content of doping radionuclides.

4 cl

The invention relates to the field of nuclear technology
The invention relates to a reactor technology for production of radioisotopes

FIELD: power industry.

SUBSTANCE: solution containing mixture of radionuclides thorium-228 and thorium-229, as well as daughter decay products of these radionuclides is bubbled with gas, thus extracting from them one of daughter decay products of thorium-228 - gaseous radionuclide radon-220. Gas is supplied through aerosol filter to sorption device where as a result of radioactive decay as per chain 220Rn→216Po→212Pb there accumulated is radionuclide lead-212, which, after attainment of saturation of activity of lead-212, is desorbed. The obtained solution is supplied to column with ion-exchange resin from which the daughter decay product of radionuclide bismuth-212 is washed from time to time. As bubbling gas there used is air and/or nitrogen and/or helium and/or argon and/or krypton and/or xenon. As sorption device there used is hollow volume the dimensions of which provide the residence time of radon-220, which is sufficient for its complete decay to radionuclide lead-212, or trap with activated carbon.

EFFECT: reducing the labour intensity of the process and the content of doping radionuclides.

4 cl

FIELD: power industry.

SUBSTANCE: solution containing radionuclides thorium-229, thorium-228 and daughter decay products of these radionuclides is bubbled with gas, thus extracting from them one of daughter radionuclides of thorium-228 - gaseous radon-220. Gas is supplied through aerosol filter to sorption device, and cleaned solution containing mixture of radionuclides thorium-228, thorium-229, as well as daughter decay products of these radionuclides are supplied to radiochemical processing by means ion-exchange resins in order to obtain target radionuclide bismuth-213. As bubbling gas there used is air and/or helium and/or argon and/or krypton and/or xenon. As sorption device there used is hollow volume the dimensions of which provide the residence time of radon-220, which is sufficient for its complete decay to stable radionuclide lead-208, or trap with activated carbon.

EFFECT: reducing the radiation dose intensity in the work area.

4 cl

FIELD: power engineering.

SUBSTANCE: method to produce a radionuclide bismuth-212 from a nitrate solution containing a mixture of radionuclides thorium-228, thorium-229 and their daughter products of decay, and release of the finished product at an ion-exchange column with cationite. The nitrate solution contains a mixture of radionuclides thorium-228 and thorium-229 and their daughter products of decay, is mixed with ethyl alcohol, this mixture is eluted via the ion exchange column with cationite, where all cations contained in the mixture are absorbed, and as bismuth-212 is accumulated, bismuth-212 is washed by diluted hydrochloric acid.

EFFECT: simplified technological process of production of a radionuclide bismuth-212.

3 cl

FIELD: physics.

SUBSTANCE: in the disclosed method of obtaining a 228Th radionuclide, which involves irradiating a target, the target material is a natural thorium isotope - 230Th, the target is placed in a linear electron accelerator and irradiated with γ-quanta of deceleration radiation, and the desired 228Th radionuclide accumulates therein during the threshold nuclear reaction 230Th(γ,2n)228Th. The target material can be 230ThF4 or 230ThO2 or 230Th metal.

EFFECT: obtaining α-radiating nuclides, which enables to eliminate shortage of therapeutic α-radiators on the market of medical radionuclides and satisfy increasing demand in the future.

2 cl

FIELD: chemistry.

SUBSTANCE: method of obtaining radioisotope 99Mo includes the irradiation of a target by a beam of neutrons with the following extraction of the target radioisotope, formed as a result of a 98Mo(n,γ)99Mo reaction. As the target applied are nanoparticles of metallic molybdenum or its compounds, insoluble in water, or a water solution of alkali, or water NH4OH solution. Irradiation of the target is carried out in water, or water alkali solution, or water NH4OH solution. The target radioisotope 99Mo is separated in the composition of an anion of water-soluble molybdate(99MoO4)-2 from nanoparticles.

EFFECT: increase of the specific activity of 99Mo radioisotope.

FIELD: physics.

SUBSTANCE: invention relates to reactor technology of producing molybdenum-99 radioisotope (99Mo), which serves a base for creation of radioisotope technetium-99m generators (99mTc). This method includes production of molybdenum-99 radioisotope at reaction 98Mo(n,γ)99Mo, carried out in a stream of slow neutron nuclear reactor and is carried out using a matrix-buffer of mesoporous inorganic materials, which channels are supplied with molybdenum compounds. Production of target is carried out by impregnation of activated carbon with specific surface area more than 300 m2/g of ammonium paramolybdate solution (NH4)6Mo7O24 and subsequent heat treatment, as a result, on the surface of the channels nano-layers MoO3 are formed. Fraction of recoil atoms 99Mo, leaving layers MoO3 and localized in the buffer depends on thickness of applied layers. Average thickness of nanolayers MoO3 applied in series into channels is set by number of applications and is limited by the effective diameter of channels. After irradiation the separation of core recoil containing activated carbon and starter nanoparticles MoO3 is achieved by elution of more than 97% MoO3 from the target 20% solution of water ammonia. Following the process of extracting cores recoil of a matrix is implemented by gasification of coal component of the matrix by combustion.

EFFECT: technical result provides simple method of making the target, higher efficiency of producing 99Mo due to creation of nano-layers over the entire volume of the matrix, which enables to achieve high homogeneity of “nanolayer-Mo - buffer”, providing efficient use of the starting material and increases efficiency of collecting recoil atoms, obtaining a uniform distribution of molybdenum in the volume of activated carbon during precipitation of molybdenum coating on surface of its mesopores.

3 cl, 1 ex

FIELD: nuclear engineering; technological processes.

SUBSTANCE: invention relates to reactor technology of producing molybdenum-99 radioisotope (99Mo), which is a base for creation of radioisotope technetium-99m of generators (99mTc). Method of producing target for production of radioisotope molybdenum-99 is carried out by reacting 98Mo(n,γ)99Mo flowing in a stream of slow neutron nuclear reactor, using a matrix-buffer of mesoporous inorganic materials, in channels which are fed molybdenum compounds. Production of target is carried out by impregnation of sorbent Al2O3 with specific surface area of 200 m2/g with ammonium paramolybdate solution (NH4)6Mo7O24 and subsequent thermal treatment in a stream of oxygen, resulting in formation on surface of channels of a nanolayer of MoO3. Average thickness of nanolayers MoO3 applied in series into channels is set by number of applications and is limited by effective diameter of channels. After irradiation separation containing core recoil buffer Al2O3 and starter nanoparticles MoO3 is achieved by elution of more than 97 % MoO3 from target with 20 % solution of ammonia in water.

EFFECT: obtaining a uniform distribution of molybdenum in volume of Al2O3 during precipitation of molybdenum coating on surface of its mesopores, simple method of making a target, higher efficiency of producing 99Mo due to creation of nanolayers over entire volume of matrix, achieving high homogeneity of “nanolayer-Mo - buffer” with high efficiency of using starting material and collection of recoil atoms.

3 cl, 1 tbl, 1 ex

FIELD: medicine.

SUBSTANCE: claimed invention provides application of an annular tank for a fissionable solution surrounding the neutron generator. An annular solution tank with an inner wall forming an inner periphery and an opposing outer wall that forming an outer periphery is also provided. Both walls run along the common central axis. In addition, the first annular cooling jacket being in a thermal contact with the annular tank inner wall and the second annular cooling jacket in a thermal contact with the annular tank outer wall are envisaged. Chilled water circulates in the said first and second cooling jackets. A chamber that runs along the central axis within the inner periphery is used as well. The target material located in the said chamber and generating neutrons passing radially outward from the chamber, and an aqueous suspension of nuclear material located between the inner and outer walls of the annular solution tank. Neutrons from the target material enter this suspension.

EFFECT: increased radiation safety due to optimisation of cooling, a possibility to work with materials of low concentration.

18 cl, 7 dwg, 1 ex

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