12 results about "Liquid scintillation counting" patented technology

The invention relates to a method for testing the tritium release rate of a tritium-containing waste package, and the method comprises the steps: guiding tritium-containing waste gas released by the tritium-containing waste package in an exhaust hood to be continuously input into an ionization chamber online monitoring system, and determining the initial tritium activity concentration; when the first threshold value is lower than the first threshold value, the tritium-containing waste gas flows into an initial bubbling sampler after passing through a refrigerating system to collect tritiated water, and target gas is obtained; enabling the target gas to circularly pass through the operation of the initial bubbling sampler, and replacing a new bubbling sampler every time a first preset time is reached; after a second preset time is reached, stopping the cyclic operation, and testing the target tritium activity concentration of liquid in the bubbling sampler which is replaced for multiple times and the current bubbling sampler by adopting a liquid scintillation counter; and calculating the tritium release rate based on the target tritium activity concentration. Target gas is discharged into the exhaust hood again, tritiated water absorption is carried out on tritium-containing waste gas multiple times, and the technical effects that tritiated water absorption is more complete due to multiple times of cyclic absorption, and the tritium release rate detection result is more accurate are achieved.

The invention relates to the technical field of nuclear material analysis, in particular to a plutonium solution specific activity determination method and application, and the plutonium solution specific activity determination method comprises the following steps: taking a plutonium solution with known specific activity A1 as a standard solution, determining the liquid flash counting rate of the standard solution, and recording the liquid flash counting rate as C1; obtaining a second-order conductance spectrum of the standard solution by using an ultraviolet-visible absorption spectrum method, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the standard solution, and recording the peak area as S1; measuring the liquid flash counting rate of the to-be-measured solution, and recording the liquid flash counting rate as C2; obtaining a second-order conductance spectrum of the to-be-detected solution by using an ultraviolet-visible absorption spectrometry, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the to-be-detected solution, and recording the peak area as S2; and calculating the specific activity A2 of the solution to be detected according to the following formula. According to the method, liquid scintillation counting and ultraviolet-visible spectrophotometry are combined, so that combination of activity response and concentration response is realized, and acquisition of isotope composition of a plutonium solution to be detected and complex sample pretreatment are not needed.

The utility model relates to a sample box and a liquid scintillation counter, comprising a housing, the housing comprises an accommodating cavity, the accommodating cavity is internally provided with a temperature adjusting member, a controller and a first conducting strip, and the temperature adjusting member and the first conducting strip are both connected with the controller; and the accommodating part is provided with an accommodating hole, the accommodating part is in sliding connection with the shell and can be located in the accommodating cavity, one side of the accommodating part is provided with a conductive plate, and the conductive plate can abut against the first conductive sheet. According to the sample box and the liquid scintillation counter, samples can be prevented from being illuminated in the storage and moving process.

The embodiment of the utility model discloses an ultra-low background liquid scintillation counter, which comprises three main photomultipliers which are radially arranged in the same horizontal plane at equal intervals, and a counting chamber for measurement is formed among the end parts of the three main photomultipliers; the number of the auxiliary photomultipliers is three, each auxiliary photomultiplier is arranged between two adjacent main photomultipliers at equal intervals, and the auxiliary photomultipliers and the main photomultipliers are arranged in a one-to-one correspondence mode and located in the same horizontal plane. Three through hole structures which are arranged at equal intervals are arranged on the side wall of the plastic scintillator at intervals and are used for adaptively arranging the three main photomultipliers, and three concave structures which are arranged at equal intervals are arranged on the side wall of the plastic scintillator at intervals and are used for adaptively arranging the end parts of the auxiliary photomultipliers; a lead shield; the photomultiplier has a shape and a structure matched with the main photomultiplier, the auxiliary photomultiplier and the plastic scintillator; a copper lining layer is adaptively arranged between the lead shielding body and the plastic scintillator; and the outer shell is adaptively arranged outside the lead shielding body.

The embodiment of the present application provides an analysis measurement method for measuring the tritium concentration in a spent fuel dissolving solution, and the analysis measurement method comprises the following steps: diluting and distilling the spent fuel dissolving solution to obtain a distillation distillate; adding the distillation distillate into a tritium column for filtering to obtain a target solution; adding a liquid scintillation liquid into the target solution for mixing, and obtaining a measurement result through a liquid scintillation counter; and obtaining the tritium concentration according to the measurement result. The analysis method of the embodiment of the present application has high accuracy in measuring the tritium concentration in the spent fuel dissolving solution.

The utility model relates to a sample detection device, which comprises a detection part, a sample detection part and a sample detection part, the supporting plate is provided with a guide channel, the supporting plate is connected with a first guide pipe, the first guide pipe is located in the detection channel, the guide channel is communicated with the first guide pipe, the end of the first guide pipe is slidably connected with a movable block, and the movable block is provided with an air hole; a moving chain is in sliding connection with the supporting plate and the first guide pipe, and the moving chain can extend into the detection channel and abut against the movable block; the output end of the first driving part is connected with the moving chain; the output end of the second driving piece is connected with a movable rod in a matched mode, the movable rod can slide in the first guide pipe and the guide channel, and the calibration piece is connected to the end of the movable rod; a cleaning plate is connected with the supporting plate, the cleaning plate is provided with a cleaning channel, and a connecting valve is arranged at the end of the cleaning channel. The sample detection device disclosed by the utility model can be used for quickly cleaning the liquid scintillation counter.

1. The name of the design product: liquid scintillation counter. 2. The use of the design product: the design product is used in liquid scintillation counter measuring equipment. 3. The design points of the design product: the combination of shape and color. 4. The picture or photo that best shows the design points: perspective view. 5. The design for which protection is sought includes color. 6. Other circumstances that need to be explained: the material of the design product is mainly aluminum plate, and the surface is subjected to anodic oxidation and sand blasting treatment.

This invention discloses a method for identifying the bio-based properties of liquid fuels based on a liquid scintillation counter. 14 C isotope analysis is used to determine the bio-based content of liquid fuels, thereby identifying whether the liquid fuel is bio-based, fossil-based, or a mixture of bio-based and fossil-based. The steps include: S1, optimizing the experimental parameters of the liquid scintillation counter; S2, determining the sample counting efficiency; S3, determining the background sample... 14 β decay count of C; S4, calculate the bio-based content of the sample using a combination formula.

The embodiment of the invention discloses an alpha and beta particle discrimination method and system based on a liquid scintillation counter. The system comprises a signal detection module used for detecting alpha and beta particle electric signals; the signal shaping circuit module is connected with the signal detection module and is used for shaping the detected alpha and beta particle electric signals; a peak holding circuit module; the peak holding module is connected with the signal shaping circuit module and is used for carrying out amplification peak holding processing on the shaped alpha and beta particle electric signals; a signal discrimination circuit module; the signal processing circuit module is respectively connected with the signal shaping circuit module and the peak holding circuit module and is used for identifying electric signals useful for alpha and beta particles; an FPGA data processing module; and the signal discriminating circuit module is connected with the signal discriminating circuit module and is used for discriminating the square wave signals corresponding to the alpha particles and the beta particles.

This invention discloses a method for assessing lipid reesterification, belonging to the field of biochemistry. Based on radioisotope-labeled assisted liquid scintillation counting technology, this invention provides a method for evaluating the reesterification of functional lipids. For the reaction of fatty acids with coenzyme A to form acyl-CoA, coenzyme A is labeled with a radioisotope, and the reesterification rate of fatty acids is quantified by calculating the isotope recovery rate in the product. For the reaction of sterols with acyl-CoA to form sterol fatty acid esters, sterols and acyl-CoA are labeled with two different isotopes respectively. The reduction of acyl-CoA in the reactants and the formation of sterol fatty acid esters in the product are characterized by detecting the intensity of the two isotopes simultaneously carried in the product, thus quantifying the reesterification rate of sterols. This invention uses labeled coenzyme A as an evaluator for the metabolic process, precisely locating the lipid metabolic pathway to the esterification reaction involving coenzyme A, eliminating the influence of unknown metabolic pathways.

This invention relates to a combined analytical method for iron-55 and nickel-63 in urine samples, which involves adding concentrated hydrochloric acid and Fe... 3+ Ni 2+ The urine sample underwent pretreatment with hydrogen peroxide, followed by oxidation with hydrogen peroxide and co-precipitation with sodium hydroxide. The sample was then purified by separation and purification using anion exchange resin combined with dimethylglyoxime precipitation. 55 Fe and 63 Ni, after purification 55 Fe and 63 Ni was measured using a liquid scintillation counter. The method of this invention was applied to a set of eight urine samples. 55 Fe、 63 The radiochemical separation process for Ni requires only 5 hours, making it a rapid and accurate combined measurement method that can simultaneously achieve... 55 Fe and 63 The detection of two radioactive elements, Ni, overcomes the limitations of existing technologies for measuring nitrogen in urine samples. 55 The Fe method is time-consuming and cannot measure simultaneously. 55 Fe and 63 Ni deficiency.

This invention discloses a method for detecting the specific activity of C14 barium carbonate, belonging to the field of radioactivity detection technology. The method includes: dissolving a C14 barium carbonate sample in a weak acid solution to generate a test solution containing bicarbonate ions; then directly mixing the test solution with a scintillation fluid to obtain a scintillation sample; finally, measuring its radioactivity activity using a liquid scintillation counter and calculating the specific activity based on a standard curve. This invention uses a weak acid to dissolve the C14 barium carbonate sample to generate a test solution containing bicarbonate ions that is directly mixed with the scintillation fluid, omitting the alkaline absorption step and simplifying the detection process from four steps in existing methods to two steps. Furthermore, it eliminates the need for a sealed gas absorption device, removing accumulated errors during sample transfer and the additional background introduced by the alkaline solution. Therefore, this invention reduces equipment requirements and improves detection accuracy and ease of operation.