150 results about "Thorium" patented technology

The invention relates to a crown ether covalent organic framework material as well as a preparation method and application thereof. The preparation method comprises the following steps: dissolving a crown ether monomer and an amino monomer in an o-dichlorobenzene solvent, adding a catalyst acetic acid aqueous solution, and uniformly dispersing to form a reaction solution; the method comprises the following steps: freezing a reaction solution through a liquid nitrogen bath, vacuumizing, filling nitrogen, carrying out a heating reaction, and carrying out post-treatment operations such as washing and drying on a reaction product, so as to obtain the crown ether covalent organic framework material BADT-DB18C6-COF. The crown ether covalent organic framework material is formed by condensation of a crown ether aldehyde monomer and an amino monomer, the crown ether monomer is 4, 4 ', 4' ', 4 '''-(6, 7, 9, 10, 17, 18, 20, 21-octahydrodibenzo [B, K] [1, 4, 7, 10, 13, 16] hexaoxacyclo octadecene-2, 3, 13, 14-tetrayl) tetrabenzaldehyde, and the crown ether monomer is 4, 4 ', 4' ', 4'''-(6, 7, 9, 10, 17, 18, 20, 21-octahydrodibenzo [B, K] [1, 4, 7, 10, 13, 16] hexaoxacyclo octadecene-2, 3, 13, 14-tetrayl) tetrabenzaldehyde. The amino monomer is 4 ', 5'-bis (4-aminophenyl)-[1, 1 ': 2', 1 ''-terphenyl]-4, 4''-diamine. The crown ether covalent organic framework material BADT-DB18C6-COF prepared by the invention is mainly used as an adsorbent, is used for adsorbing and recovering uranium, thorium and americium ions from a solution, shows good adsorption capacity on radionuclides U-238, Th-232 and Am-243, and is particularly suitable for the field of spent fuel post-treatment in the nuclear industry.

The invention discloses carboxyl-rich chitosan gel and preparation thereof and separation and enrichment of radioactive element thorium, and the method comprises the following steps: mixing and dissolving chitosan, water and glacial acetic acid, adding 1, 2, 3, 4-butanetetracarboxylic acid, and uniformly mixing; heating at 80 DEG C to completely volatilize moisture, and heating to 100 DEG C for reaction to obtain a solid product; taking out a solid product, soaking the solid product in deionized water, and performing freeze drying treatment to obtain the carboxyl-rich chitosan gel, namely the CCS-BTCA xerogel. The problems that an existing adsorbent is poor in stability and low in adsorption activity are solved, the prepared material has the high adsorption rate, the optimal adsorption effect can be achieved at the temperature of 298 K and the pH value of 3, the adsorption capacity is 228.9 mg / g, and the maximum theoretical adsorption capacity can reach 279.4 mg / g.

Systems and methods for generating radionuclides, such as radium-224. Systems herein may include a first cartridge having a first opening, a second opening, and a chamber therebetween having a first resin having affinity for thorium-228 and bismuth-212; a second cartridge having a first opening, a second opening, and a chamber therebetween having a second resin having affinity for thorium-228 and bismuth-212, a third cartridge having a first opening, a second opening, and a chamber therebetween comprising a third resin having affinity for thorium-228 and bismuth-212, a fourth cartridge having a first opening, a second opening, and a chamber therebetween having a third resin having affinity for lead-212; wherein a continuous flow path is formed from a top of the first cartridge though the second cartridge, through the third cartridge, and to a bottom of the fourth cartridge during system use.

The invention belongs to the field of medical isotope separation and preparation, and particularly relates to a method for separating and purifying < 212 > Pb from a thorium solution, which comprises the following steps: 1) leacheate is introduced into a Pb selective adsorption column to pretreat the Pb selective adsorption column, and then < 232 > Th salt solution and leacheate are introduced in sequence; 2) continuously introducing a desorption solution into the Pb selective adsorption column, enabling the desorption solution passing through the Pb selective adsorption column to flow into the Th selective adsorption column, and collecting the outflowing desorption solution; a desorption solution only containing 212Pb is obtained; according to the method, the 212Pb in the high-concentration thorium solution can be separated and purified at the same time. While < 232 > Th impurity entrainment and pollution in a < 212 > Pb product are remarkably reduced, compared with a single-column process, the separation time is basically not increased. The separated 212Pb product has high radionuclide purity and chemical purity at the same time, and can meet related pharmaceutical requirements.

The present application belongs to a kind of medical radioisotope preparation field, specifically related to a kind of method for extracting lead-212 and bismuth-212 in thorium-232 decay chain, solution containing thorium-232 decay chain material is passed through anion exchange resin column, the solution containing thorium-232 decay chain material includes halogen ion, and the concentration of hydrogen ion in the solution containing thorium-232 decay chain material is greater than 0.01mol / L, lead-212 and bismuth-212 are absorbed by anion exchange resin column, and other nuclides directly pass through anion exchange resin column and are not absorbed, lead-212 and bismuth-212 are desorbed from anion exchange resin column by elution reagent, and lead-212 and bismuth-212 are separated and extracted;The present application can extract lead-212 and bismuth-212 simultaneously, and the extraction speed is fast, the purity is high, and the product is not easy to cause organic pollution.

The invention relates to a method for machine learning aided design of a structural alloy for a fourth-generation thorium-based molten salt reactor, and belongs to the technical field of artificial intelligence auxiliary material design. The method comprises the steps that S1, an alloy component machine learning model for phase composition prediction is established, specifically, based on known alloy sample data, the sample data comprise alloy element content and corresponding phase composition information, and the machine learning model used for predicting alloy phase composition is established; s2, screening an initial alloy component space through phase composition constraint conditions; s3, secondary screening of alloy components based on thermodynamic simulation; s4, alloy sample preparation and solid solution homogenization treatment; s5, carrying out a mechanical property test; and S6, experimental result feedback and machine learning model closed-loop updating are carried out. According to the method, the artificial intelligence technology and the traditional alloy design theory are organically fused, an efficient and reliable new path is provided for research and development of key structural materials for the fourth-generation thorium-based molten salt reactor, and the important scientific research value and the engineering application prospect are achieved.

This invention discloses a Th / Ra generator containing natural thorium and its production. 224 The Ra method. The generator of this invention includes a cation exchange resin column and bottles I to VI; wherein bottle I is filled with the stock solution; bottle III is filled with deionized water; bottle IV is filled with 4.0–6.0 M nitric acid; bottles II, V, and VI are empty; bottle V is a specially designed collection bottle with an extraction resin column at its opening for collection. 224 Ra. The method of the present invention includes the following steps: 1) using a mixture containing 228 1) A natural thorium mixture of Th and Ra was concentrated to obtain a concentrate, and then the pH of the system was adjusted to serve as the packing stock solution for the Th / Ra generator; 2) The stock solution was passed through a cation exchange resin column to obtain a cation exchange resin column loaded with thorium. 224 Ra, and collect the eluent from the original solution for later use; 3) Elute the cation exchange resin column with inorganic acid. 224 Ra, then the eluent is collected using a special collection bottle to obtain... 224 Ra. This invention enables the separation, purification, and recycling of [product name]. 224 Ra, to overcome 228 Th / 224 The Ra generator has a stringent loading process to avoid the radioactive risks associated with handling tons of natural thorium.

The application relates to the technical field of quartz crystal purification, and particularly discloses a method for eliminating radioactive elements in quartz crystals, which comprises the following steps: adding quartz sand into a composite cleaning solution, stirring and cleaning, then performing solid-liquid separation and water washing to obtain pretreated quartz sand; performing heat treatment on the pretreated quartz sand in an oxygen-containing atmosphere at 850-1000 DEG C for 2-4 hours to obtain heat-treated quartz sand; rapidly cooling the heat-treated quartz sand in cooling water at 10-30 DEG C for 15-30 seconds, then crushing and screening to obtain crushed quartz sand; adding the crushed quartz sand into a selective acid cleaning solution under stirring to perform an acid cleaning reaction, then performing solid-liquid separation, washing and drying after the reaction to obtain low-radioactivity quartz sand. The composite cleaning solution and the selective acid cleaning solution are used in cooperation to efficiently remove radioactive elements such as uranium and thorium in the quartz crystals, and the physical and chemical properties of the quartz crystals can meet the requirements of high-end semiconductor and optical applications.

Provided are: high-purity alumina particles which have improved purity by reducing the amount of impurities remaining in alumina particles derived from metallic aluminum and also by reducing the amount of metallic aluminum; and a method for producing the high-purity alumina particles. The aluminum oxide particles derived from metallic aluminum have a uranium element content of not more than 5 ppb, a thorium element content of not more than 5 ppb, a metallic aluminum content of not more than 5 ppm, a sodium content of not more than 10 ppm, and an iron content of not more than 10 ppm, and a metallic aluminum powder is introduced into a flame to be gasified and oxidized, and is spheroidized by surface tension during cooling to form spherical aluminum oxide particles. Spherical alumina particles are introduced into an alkaline solution to dissolve metallic aluminum remaining in the particles, and the spherical alumina particles are dried.

The application relates to a thorium and spallation element separation method, which comprises the following steps: injecting a thorium-based solution into column 1 to obtain a first effluent, washing column 1 with a first inorganic acid solution and a second inorganic acid solution in sequence to obtain a first washing solution and a first thorium solution respectively; injecting the first thorium solution into column 2 to obtain a second effluent, washing column 2 with a third inorganic acid solution and a second inorganic acid solution in sequence to obtain a second washing solution and a second thorium solution; mixing the first thorium solution and the second thorium solution, injecting into column 3 to obtain a third effluent, and washing column 3 with a fourth inorganic acid solution to obtain a third thorium solution. The method does not introduce other foreign reagents and is not polluted by foreign impurity ions, and the high ion potential of Th is utilized to preferentially adsorb on a cation column to achieve the purpose of separation from other spallation elements.

The application discloses a kind of uranium nuclide automatic extraction device and method, wherein, device includes dissolving target device, acid regulator, extractor, purifier, waste liquid tank, product tank, control system and shielding box, dissolving target device, acid regulator, extractor, purifier, waste liquid tank, product tank are connected by conveying pipe and valve, liquid conveying power is provided by peristaltic pump, control system is set in shielding box, and relevant components in shielding box are electrically connected.The application also describes a method for extracting a uranium nuclide solution substantially free of impurities from an irradiated thorium target material.The uranium nuclide automatic extraction device of the present application can achieve rapid and efficient extraction and purification of uranium nuclides from irradiated thorium target material.The device has the characteristics of simple structure, compactness and automation operation, which greatly improves the production efficiency and reduces the radiation dose received by the operator.

This invention relates to an aminophosphonate-functionalized carbon material, its preparation method, and its uses. The aminophosphonate-functionalized carbon material comprises a carbon matrix and a structure of Formula I covalently linked to the carbon matrix. It can be applied to capacitive deionization technology to selectively adsorb thorium from a mixed solution containing thorium and rare earth elements, exhibiting a high adsorption capacity for thorium.

Voltage power source device having a connected structure in which each one of ends of a first metal and a second metal that generate the Seebeck effect are connected by a one-end side bonding part in which uranium and thorium are supported on a carrier made of boron, and the other ends are connected by an other bonding part in which uranium and thorium are supported on a carrier made of carbon. The one-end side bonding part is raised to a first temperature through α-decay of uranium (U) and thorium (Th), and the other bonding part is raised to a second temperature that is different from the first temperature through α-decay of uranium (U) and thorium (Th), whereby a current is generated by the Seebeck effect based on the relative temperature difference between the two bonding parts. Voltage power source device and power generation method enable next-generation type energy supply.

This invention belongs to the field of uranium resource exploration technology, specifically relating to a method and apparatus for detecting gamma rays. The method includes: utilizing... 241 The equivalent peak position after the interaction of Am and NaI(Tl) crystals serves as a self-stabilizing peak, providing a stable gamma-ray reference peak and achieving automatic spectrum stabilization. A digital high-speed multichannel module acquires gamma-ray signals, achieving full acquisition of gamma-ray signals in the energy range of 30keV to 3000keV. Multiple Regions of Interest (ROIs) are set for the acquired gamma-ray signals using digital energy thresholds, obtaining CPS counts for the quantitative gamma energy range, the natural gamma energy range, and the uranium-thorium-potassium (UHT) energy range of the gamma spectrum. Using the calibration coefficients of each parameter in the standard model, and based on the CPS counts for the quantitative gamma energy range, the natural gamma energy range, and the UHT / UHT energy range of the gamma spectrum, the quantitative gamma, natural gamma, and gamma spectrum detection results are output. This invention enables a single probe to simultaneously output measured data for quantitative gamma, natural gamma, and gamma spectra, improving the efficiency of acquiring these data.

The invention discloses a preparation method of 5N-grade ultra-pure lutetium oxide, which comprises the following steps: removing thorium and uranium from a lutetium chloride solution, carrying out primary precipitation with oxalic acid, firing to obtain a primary lutetium oxide product, re-dissolving the primary lutetium oxide product with nitric acid, carrying out secondary precipitation with ammonia water, and firing to obtain the 5N-grade ultra-pure lutetium oxide. According to the method disclosed by the invention, the preparation of lutetium oxide with higher purity can be realized by combining extraction with impurity grading removal of oxalic acid-ammonia water double precipitation so as to meet quality index requirements required by application of materials with higher performance. The preparation method is high in stability, high in yield and suitable for industrial production and application.

The invention relates to wet preparation of a radiation therapy source and a method for accumulating radium radionuclides. The method comprises providing a first solution comprising a thorium radionuclide and a thorium binding extractant, wherein the first solution does not bind to radium; allowing a portion of the thorium radionuclides in the first solution to decay to radium atoms; and collecting radium atoms resulting from the decay. The collected radium atoms may be contained in a solution into which a brachytherapy source is immersed in a manner that collects radium atoms onto the brachytherapy source.

The present invention discloses a preparation method and application of a thorium-based MOF material modified by an ionic liquid. The preparation method comprises the following steps: (1) reacting a water-soluble thorium salt with tetrakis[4-(4'-carboxylphenyl)phenyl]ethylene in the presence of an acidic regulator and a solvent to obtain a thorium-based MOF material; (2) reacting the thorium-based MOF material with an ionic liquid in the presence of a solvent to obtain an ionic liquid-modified thorium-based MOF material; the ionic liquid is a terminal halogenated 1-alkyl 3-methylimidazolium ionic liquid [MIM(CH2) n X]Y, wherein n=2-6, X is Cl, Br or I, and Y is Cl, Br or I. The thorium-based MOF material and the thorium-based MOF material modified by the above method both have stable crystalline structures. The thorium-based MOF material modified by the end-group halide ionic liquid exhibits excellent photocurrent response and has multiple active sites. It can be used as a photocatalyst to efficiently catalyze the reduction of carbon dioxide to carbon monoxide and methane, and exhibits good cyclic stability.

The present application relates to a kind of carbonate lithology identification method based on well logging parameter, device and storage medium, belong to rock type identification technical field, the method includes: the multiple carbonate thin section of target formation is calibrated, obtains the well logging parameter and type of corresponding depth of carbonate thin section;Carbonate thin section includes dolomite thin section and limestone thin section;Based on the well logging parameter of corresponding depth of carbonate thin section plot crossplot, and determine target parameter according to crossplot and type;Target parameter includes uranium value, thorium value, acoustic time difference and compensation neutron;Based on target parameter, the lithology of dolomite and limestone in non-coring section is identified.The present application provides the carbonate lithology identification method based on well logging parameter, is analyzed with multiple parameters such as uranium, thorium, acoustic time difference and compensation neutron, realizes accurate identification to carbonate lithology.

The invention discloses a method for extracting and separating rare earth, iron and uranium in monazite excellent molten slag, which comprises the following steps: step 1, a hydrochloric acid complete dissolution step: realizing preliminary release of valuable elements in the monazite excellent molten slag; 2, oxalic acid precipitation, wherein specific separation and solution purification of thorium are achieved; 3, primary uranium extraction is conducted, and preliminary separation of rare earth elements and uranium iron is achieved; step 4, a rare earth recovery step; 5, back extraction is carried out, and preliminary enrichment of uranium and iron is achieved; 6, secondary extraction of uranium to realize uranium-iron separation; step 7, iron precipitation; step 8, uranium back extraction; and 9, uranium product forming. The method aims at achieving step-by-step extraction and separation of rare earth, iron and uranium in the leaching solution of the optimal dissolving slag, the problem that uranium and iron are difficult to separate in the existing extraction process is solved, and the recovery rate of valuable elements of rare earth and uranium is increased.

The invention relates to the technical field of metal target material preparation, and discloses a cylindrical metal thorium target material preparation method, which comprises: taking metal thorium powder, placing into a cylindrical mold, carrying out static pressure molding, and demolding to obtain a metal thorium blank; taking a plurality of metal thorium plain blanks, stacking the metal thorium plain blanks in a cylindrical crucible, placing the cylindrical crucible in smelting equipment, vacuumizing to a negative pressure state, then heating for smelting, after the metal thorium plain blanks are completely molten, filling inert gas until the interior of the smelting equipment is in a positive pressure state, stopping smelting, and after the smelting equipment is cooled to the room temperature, taking out the metal thorium plain blanks; taking out a cylindrical metal thorium target material crude product; and the cylindrical metal thorium target material crude product is machined, and the cylindrical metal thorium target material is obtained. The method has the following technical effects that the multiple metal thorium plain blanks are stacked in the cylindrical crucible to be smelted, and the problems that the upper and lower compactness of the metal thorium plain blanks is inconsistent, and demolding is difficult can be solved. Inert gas is filled in the smelting process, so that air holes in the metal thorium target material can be eliminated, and the compactness is improved.

The invention discloses a monazite smelting laboratory wastewater treatment method, which comprises: 1, controlling the temperature of laboratory wastewater at 30-90 DEG C, adding an alkali cake, carrying out a stirring reaction for 0.5-2 h, and after the reaction is completed, carrying out solid-liquid separation to obtain a phosphorus removal wastewater filtrate and a phosphorus-rare earth co-precipitation filter residue; 2, the filtrate in the step 1 is subjected to adsorption treatment through a silica gel adsorption column, adsorption tail liquid is obtained, and the total amount of thorium and uranium in the adsorption tail liquid is reduced to 0.3 ppm or below; and step 3, transferring the adsorption tail liquid into an ozone column, filling the ozone column with a silicon-aluminum compound catalyst material, and continuously introducing ozone into the ozone column through an ozone generator so as to reduce the COD value in the adsorption tail liquid to below 50ppm through ozone oxidation, thereby finally obtaining qualified treated liquid. The invention aims to reduce laboratory wastewater radionuclides, namely uranium, thorium, phosphorus and COD (Chemical Oxygen Demand).

The embodiment of the invention relates to the field of testing or analyzing ground materials by means of measuring chemical or physical properties of materials, in particular to a method for circling a metallogenic prospective area of a sandstone type uranium ore in a sedimentary basin. According to the method, soil samples with different granularities are obtained, the content of uranium and the content of thorium in the soil samples are determined respectively, and the potential value of deep uranium mineralization of each sampling point is obtained so as to indicate the deep uranium mineralization potential of a sampling area; by analyzing the molybdenum content in the soil sample with the small granularity, deep metallogenic information of the sampling area is further reflected through the abnormity of the molybdenum content; according to the potential value and the molybdenum content of deep uranium mineralization, deep uranium mineralization information can be reflected more comprehensively, and the accuracy of circling a mineralization prospective area is improved; in the implementation process, only superficial soil samples need to be collected, the field work difficulty is reduced, and the uranium prospecting efficiency is improved.

The invention discloses a carboxyl-functionalized metal organic framework material and preparation and application thereof in treatment of thorium-containing wastewater, and the method comprises the following steps: adding MIL-101-Cl and amino acid into an organic solvent, carrying out ultrasonic dispersion, adding triethylamine, and stirring; reacting at 100 DEG C, centrifuging, washing, and carrying out vacuum drying at 50-70 DEG C; the MIL-101-Cl is prepared by carrying out a reaction on MIL-101 powder, paraformaldehyde, tin tetrachloride and trimethylchlorosilane in anhydrous dichloromethane. The problems that in the prior art, the structure is disordered, stability is poor, selectivity is lost, and industrialization is difficult are solved. According to the invention, a carboxyl donor is grafted on the surface of chloromethylated MIL-101, and meanwhile, the increase of the carboxyl content obviously enhances the adsorption capacity of the material; due to the increase of the carboxyl density, the MIL-101-2COOH has more excellent Th (IV) adsorption selectivity and chemical stability.

The invention discloses a method for recovering uranium and rare earth from superior dissolving slag, which comprises the following steps: step 1, mixing the superior dissolving slag of monazite with a hydrochloric acid solution for acid leaching, and filtering to obtain leached filtrate and a filter cake; 2, sodium chloride is added into the leaching filtrate, so that the chloride ion concentration reaches 140-150 g / L, and an adsorption stock solution is obtained; 3, the adsorption stock solution is subjected to uranium adsorption operation through strongly basic anion resin until the resin is saturated, and saturated resin and adsorption tail liquid are obtained; 4, the saturated resin is washed, leached, subjected to impurity removal and precipitated, and sodium diuranate is obtained; 5, oxalic acid is added into the adsorption tail liquid to precipitate thorium, and thorium oxalate precipitate and filtrate after thorium precipitation are obtained after solid-liquid separation; and step 6, carrying out rare earth precipitation on part of the filtrate after thorium precipitation in the step 5 to obtain a rare earth product. The invention aims to convert traditional'wastewater 'into valuable resources through internal circulation and recycling.

Thorium-based fuel bundles are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300 / 600 / 900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt%. Reprocessing of spent fuel bundles is also avoided.

The application relates to a sandstone type uranium ore enrichment zone determination method and device and a storage medium. The method comprises the following steps: obtaining the thorium element content in a spectral logging; calculating the uranium element content according to the thorium element content; calculating a sedimentary environment factor; calculating a clay mineral relative content factor; calculating a argillaceous content factor; calculating an organic matter content factor curve; calculating a ore-controlling comprehensive evaluation parameter; and determining a uranium abnormal enrichment section. The sandstone type uranium ore enrichment zone determination method, device and storage medium provided by the embodiment of the application can effectively calculate the ore body enrichment depth, thereby reducing the exploration cost, improving the exploration success rate, and being applicable to new area exploration, and having high popularization and application value.

The invention discloses a thorium-doped strontium tetraborate crystal as well as a preparation method and application thereof, the chemical formula of the thorium-doped strontium tetraborate crystal is ThxSr1-xB4 + yO7 (Th SBO), and the thorium-doped strontium tetraborate crystal grows by adopting a solution method. The Th: SBO crystal disclosed by the invention is low in melting point, simple in component and beneficial to realizing high-quality crystal growth; the material has a wide band gap, has high transmittance in a vacuum ultraviolet band, is beneficial to reduction of absorption loss in a nuclear transition luminescence band, and is beneficial to excitation and detection of a nuclear transition signal; the SBO crystal is a random quasi-phase matching (RQPM) nonlinear optical crystal, 296.76 nm narrow linewidth laser 148.38 nm frequency doubling light can be used as an excitation source of the nuclear light clock through frequency doubling, and a Th host crystal and a frequency doubling crystal are combined, so that the complexity of a system is remarkably simplified, and a core material is provided for miniaturization of the nuclear light clock.

The application relates to a processing method of monazite acid-dissolved slag, which comprises the following steps: mixing monazite acid-dissolved slag and water, then performing separation, mixing acid-dissolved slag light mud obtained through the separation with a hydrochloric acid solution and a reducing agent, performing acid dissolution, then performing first solid-liquid separation, and obtaining first filtrate; the mass concentration of the hydrochloric acid solution is 15%-25%, the volume of the hydrochloric acid solution is 3m 3 / 1000kg-5m 3 / 1000kg, the mass of the acid-dissolved slag light mud is 1000kg; the first filtrate is mixed with an oxidizing agent to perform oxidation reaction, then the obtained oxidation reaction liquid is mixed with a phosphorus source to perform first precipitation treatment, then second solid-liquid separation is performed, and iron precipitate and second filtrate are obtained; a first pH regulator is used to adjust the pH value of the second filtrate to 3.8-4.2, then hydrogen peroxide is added to perform second precipitation treatment, then third solid-liquid separation is performed, and thorium-uranium precipitate and third filtrate are obtained; the third filtrate is mixed with a rare earth precipitating agent to perform third precipitation treatment, and rare earth precipitate is obtained.

The invention relates to the technical field of metal target material preparation, and discloses a preparation method of a high-compactness metal thorium target material, which comprises the following steps: taking metal thorium powder, grinding and refining, and sieving with a screen twice to obtain metal thorium fine powder; transferring the metal thorium fine powder into a mold for static pressure molding, and demolding to obtain a metal thorium blank; the metal thorium blank is placed between two inert material gaskets and placed in a sintering container, vacuum sintering is conducted in vacuum sintering equipment, and after sintering is completed, a crude product of the metal thorium target material is taken out after the vacuum sintering equipment is cooled to the room temperature; and the crude product of the metal thorium target material is machined through a grinding machine, a surface oxidation layer is removed, and the metal thorium target material is obtained. The method has the following technical effects that the fineness and uniformity of the metal thorium powder are improved through grinding refining and twice sieving, the forming capacity of the metal thorium powder is enhanced, and abnormal growth of crystal grains in the sintering process is avoided; and the inert material gasket is arranged to participate in sintering, so that sintering warping caused by non-uniform grain shrinkage is avoided.

The application discloses a high-thorium sandstone reservoir logging identification method, device and equipment and a readable storage medium. Uranium-free gamma measurement values and potassium content in a to-be-identified high-thorium sandstone reservoir are acquired, and acoustic travel time and density of the to-be-identified high-thorium sandstone reservoir are acquired. The potassium content and the uranium-free gamma measurement values are used to construct a uranium-free gamma curve without thorium influence, the uranium-free gamma curve without thorium influence is compared with a measured uranium-free gamma curve, and a high-thorium layer section is qualitatively identified in a sandstone profile and a mudstone profile. In the high-thorium layer section, the uranium-free gamma curve without thorium influence is used to quantitatively calculate shale content. According to the shale content, the acoustic travel time and the density, shale influence is eliminated, and porosity of the to-be-identified high-thorium sandstone reservoir is calculated. According to the shale content and the porosity, a reservoir is identified and divided in the high-thorium layer section, and logging identification of the to-be-identified high-thorium sandstone reservoir is completed. The application improves the calculation precision of reservoir mineral components and physical property parameters.