9 results about "Americium" 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 application discloses an ion source device for desorption of americium 241, and relates to the technical field of ion sources.The ion source device mainly comprises americium 241, a clamping device for the americium 241, an R-axis rotating platform and a sample stage.The americium 241 is installed on the clamping device for the americium 241, and the clamping device is installed on the R-axis rotating platform.A glass slide coated with a sample is installed on the sample stage, and the sample stage and the R-axis rotating platform are installed on two XYZ-axis displacement platforms, respectively, and the two XYZ-axis displacement platforms are adjusted to move in the X, Y and Z directions, respectively.The alpha particles generated by the americium 241 decay generate a series of plasmas in the air and are injected into the surface of the sample, so that the molecules on the surface of the sample are ionized and desorbed, and the ions enter a mass spectrometer through a sample inlet for detection.The relative positions of the americium 241, the sample stage and the sample inlet are adjusted, so that the mass spectrometer obtains the best ion signal, and the operation is safe and simple, and the common molecules can be rapidly detected.

The invention belongs to the technical field of nuclear fuel cycle analysis, and relates to a pretreatment process for step-by-step separation of thorium, uranium, americium and plutonium in neptunium dioxide powder, and the process comprises seven steps of sample dissolution, sample valence adjustment, Th separation, U separation, Am separation, Pu separation and content determination. According to the method, the TEEVA, UTEEVA and TRU extraction chromatography resin coupling technology is applied, and step-by-step separation of Th, U, Am and Pu in neptunium dioxide powder is achieved; measuring the content of the separated trace actinide elements by using an inductively coupled plasma mass spectrometer (ICP-MS); through the step-by-step separation pretreatment process, the adding standard recovery rate of each element of Th, U, Am and Pu is greater than 90%, and the precision of the method is superior to 10%.

The invention discloses a separation device and method for an activation product americium and a fission product antimony, tin and silver, belongs to the technical field of separation of the activation product and the fission product, and solves the technical problems that the activation product americium and the fission product antimony, tin and silver cannot be separated synchronously, the radiation risk is high, and the recovery rate and the decontamination degree are low. The separation device comprises a liquid storage tank unit, a conveying pump, a color layer separation unit, a product collection unit and a waste liquid collector which are sequentially arranged from top to bottom. And the chromatography separation unit is used for adsorbing, separating and desorbing americium, antimony, tin and silver in the radioactive solution containing americium, antimony, tin and silver. The separation method comprises the following steps: preparing a radioactive solution containing americium, antimony, tin and silver, preparing a chromatographic layer adsorption column, adsorbing americium, antimony, tin and silver, washing, separating and purifying the antimony, tin, americium and silver, and desorbing. The method is used for separating activation products of americium and fission products of antimony, tin and silver.

The invention relates to a boron-containing extraction agent, a preparation method thereof and application of the boron-containing extraction agent in critical plutonium purification prevention, and the boron-containing extraction agent is 2, 4, 6-trimethylphenoxy-bis [2-(N, N-dioctyl acetamide)] borate. According to the method, 2, 4, 6-trimethylphenol and bis [2-(N, N-dioctyl acetamide)] boric acid are used as raw materials, and the boron-containing extraction agent is prepared through a dehydration condensation reaction between phenolic hydroxyl groups and boric acid. The neutron poison B element is introduced into the amide extraction agent to obtain the anti-criticality boron-containing extraction agent; trimethylphenoxy is introduced to a central boron atom of the boron-containing extraction agent, and the boron atom with electron deficiency in the center is protected by utilizing a hyperconjugation effect and steric hindrance, so that the water stability of the boron-containing extraction agent is improved. The boron-containing extraction agent has a high-selectivity extraction effect on plutonium, and the extraction distribution ratio of uranium, americium, strontium, cesium and other fissure elements is very low; the method is suitable for separation, purification and recovery of a large amount of plutonium in a post-treatment plant and an MOX fuel preparation plant so as to eliminate the critical risk of organic phase extraction of plutonium.

The present application relates to the nuclear chemical technology field, especially to the integrated process for extracting strontium and americium from high-level liquid waste, which uses N, N, N'N'-tetraoctyl-3-oxypentanediamide (TODGA) as an extractant, and provides a new liquid-liquid extraction process with two cycles, which includes a strontium extraction cycle and an americium extraction cycle, and can extract strontium and americium from high-level liquid waste at the same time. The process of the present application includes two process links of the americium extraction cycle and the strontium extraction cycle; the americium extraction cycle includes three process steps of extracting americium, washing americium and stripping americium in sequence; the strontium extraction cycle includes three process steps of extracting strontium, washing strontium and stripping strontium in sequence.

The invention discloses a device and a method for separating activation products of americium, uranium, neptunium and plutonium, belongs to the technical field of separation of activation products, and solves the technical problems that synchronous separation and purification of americium, uranium, neptunium and plutonium cannot be realized and high-sensitivity and high-accuracy detection and analysis cannot be simultaneously met during separation of the activation products. The separation device comprises a liquid storage tank unit, a conveying pump, a color layer separation unit, a product collection unit, a waste liquid collector and a valve which are sequentially arranged from top to bottom. The waste liquid collector and the product collecting unit are positioned at the lowermost end. Liquid in the liquid storage tank unit enters the color layer separation unit through a conveying pump, and liquid flowing out of the color layer separation unit enters the product collection unit or the waste liquid collector. The separation method comprises the following steps: preparing a solution, preparing a chromatography adsorption column, adsorbing americium, uranium, neptunium and plutonium, washing, separating and purifying neptunium, leaching uranium, americium and plutonium, separating and purifying uranium, americium and plutonium, and desorbing. The method is used for separating activation products of americium, uranium, neptunium and plutonium

The invention discloses a separation device and a separation method for an activation product americium and a fission product cerium-antimony-tin, belongs to the technical field of separation of the activation product and the fission product, and solves the technical problems that the activation product americium and the fission product cerium-antimony-tin cannot be separated synchronously, the process is tedious and time-consuming, and the radiation risk is high. The separation device comprises a liquid storage tank unit, a conveying pump, a color layer separation unit, a waste liquid collector and a product collection unit which are sequentially arranged from top to bottom. Liquid in the liquid storage tank unit is conveyed to the color layer separation unit through the conveying pump, and effluent of the color layer separation unit flows to the waste liquid collector or the product collection unit or the liquid storage tank unit. The separation method comprises the following steps: preparing a radioactive solution containing americium, cerium, antimony and tin, a washing solution, a leaching solution, a desorption solution and a chromatographic layer adsorption column, adsorbing, washing and leaching the americium, cerium, antimony and tin, and separating, purifying and desorbing the cerium, tin, antimony and americium. The method is used for preparing radioactive measurement sources of cerium, antimony, tin and americium.

A method of partitioning americium that includes directing an actinide-lanthanide containing raffinate into a liquid-liquid extraction system, wherein the actinide-lanthanide containing raffinate comprises americum, curium, and one or more lanthanides in an aqueous solvent, contacting the actinide-lanthanide containing raffinate with an organic extracting solution such that the americum, the curium, and the one or more lanthanides bind with the organic extracting solution to form an actinide-lanthanide organic solution, wherein the organic extracting solution comprises an organic neutral extractant, a phase modifier, and a hydrocarbon diluent, and contacting the actinide-lanthanide organic solution with sodium bismuthate in nitric acid such that the sodium bismuthate induces an oxidation state increase in the americum from a first oxidization state to a second oxidation state such that the americum unbinds from the actinide-lanthanide organic solution, thereby partitioning the americum from the curium and the one or more lanthanides.