43 results about "Radioactive Activity" patented technology

The invention discloses a dynamic calculation method and system for a radiation field in the cutting process of an activity non-uniform radioactive source, and belongs to the field of radiation field calculation. The method comprises the following steps: acquiring three-dimensional activity distribution data of a radioactive source; constructing a voxelization model and coupling the voxelization model with an activity grid to distribute activity; establishing an LBVH hierarchical structure of the shielding body; a point kernel is generated in a self-adaptive mode through ray tracing and average free path comparison; carrying out radiation field calculation by adopting point nuclear integration, and realizing multilayer ray tracing in the radioactive source, between the sources and a shield in the process; on-line cutting and moving operation of the voxel model is supported, and the radiation field is dynamically updated. According to the method, the cutting operation of the activity non-uniform radioactive source can be simulated, the problem that the radioactive activity of each cutting product cannot be represented after cutting by a traditional method is solved, the radiation field dynamic calculation in the activity non-uniform radioactive source cutting process can be simulated, initial modeling of the radiation environment only needs to be carried out once, and the efficiency is improved. And repeated modeling is not needed.

The present disclosure relates to a method, device, storage medium and electronic device for measuring radioactivity, the method comprising: obtaining an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive objects in a target container and an absorption factor of the target container, the absorption factors representing absorption efficiencies of radioactive rays of the target radioactive objects; and determining radioactivity of the target radioactive objects according to the absorption factors of the shielding medium and the absorption factor of the target container. In this way, the radioactivity of the target radioactive objects is determined according to the absorption factors of the shielding medium and the absorption factor of the target container, thereby avoiding the problem of poor accuracy of the analysis result of the radioactivity due to non-uniform radioactivity of the plurality of target radioactive objects, and effectively improving the accuracy of the radioactivity measurement result when the plurality of target radioactive objects are non-uniform radioactive sources.

The present application relates to a kind of natural conditions under the estimation method of superuranic nuclide resuspension release source term.This application obtains the environmental characteristic parameter of the place of contaminated area, calculates the related parameter of superuranic nuclide pollution condition, calculates the surface covering layer factor of contaminated area soil, calculates the resuspension release source term of superuranic nuclide, can start from the characteristics of soil environment, nuclide characteristics, natural condition three aspects, based on the mass load theory of particulate matter, using the release flux of particulate matter in contaminated area soil and the level of radioactivity concentration in soil, the resuspension release source term of superuranic nuclide is calculated, realizes the resuspension release amount of superuranic nuclide in soil environment pollution under natural conditions is scientifically and accurately evaluated.

The utility model provides a gas purification system of a reactor. The gas purification system comprises a purification pipeline, and an inert gas adsorber, an iodine adsorber, a polonium processor, a filter and a radioactivity analyzer which are arranged on the purification pipeline. And the inert gas adsorber is used for removing inert gas in the mixed gas. The iodine adsorber is used for removing iodine in the mixed gas. The polonium processor is used for removing polonium in the mixed gas. And the filter is used for removing small particles in the mixed gas. And the radioactivity analyzer is used for detecting the radioactivity of the mixed gas. According to the gas purification system, aiming at the characteristics of radioactive substances of the metal fast reactor, a four-stage purification treatment device is arranged to remove radioactive gas in the mixed gas, and in addition, a radioactivity analyzer is further arranged and used for detecting and judging whether the radioactivity in the gas meets the emission standard or not; and the problem of radioactive substance release caused by leakage of the containment is effectively avoided.

The invention relates to the technical field of terminal sterilization and filtration in a radiopharmaceutical preparation process, in particular to a filter membrane sterilization and filtration device and system. Comprising the steps that a state sensing module collects liquid medicine radioactive activity data and filter membrane structure strain data and generates real-time data flow; the twinborn modeling module constructs a filter membrane digital twinborn body, and outputs an accumulated radiation damage prediction result through data assimilation; the prediction decision module generates a filtering parameter optimization sequence by using a deep reinforcement learning agent; the control execution module adjusts the flow velocity of the liquid medicine through fuzzy self-adaptive PID control and feed-forward compensation; and the verification feedback module performs an integrity test and transmits data back to the twin modeling module to realize model parameter correction. All the modules form a closed-loop control system through a high-speed data bus, so that the damage of radiation to a filter membrane material is effectively inhibited, and the integrity and the sterile guarantee level of a membrane structure in the filtering process are maintained.

A method and an apparatus for producing radionuclide-containing products having substantially the identical desired activity of radioactivity at different times of application, with respect to a given calibration time. The method according to the invention allows to ensure a consistent composition of the desired radionuclide-labeled pharmaceutical at all times of application within the shelf life through a single manufacturing process. With the present invention it is possible, for example, to provide [n.c.a. Lu-177]Lu-DOTATOC on each working day of the week with constant activity at the respective time of application in a single manufacturing step.

The present disclosure relates to a radioactive waste barrel activity measuring device, comprising a chassis and a conveying mechanism arranged on the chassis, the bottom of the chassis is connected with walking wheels, a dose measuring mechanism and a detector assembly are arranged on one side of the conveying mechanism on the chassis, the detector assembly is movably arranged on the chassis to be able to approach or move away from the conveying mechanism, a control system is further arranged on the chassis, and the control system is electrically connected with the dose measuring mechanism and the detector assembly respectively. In this way, the device can conveniently adjust the waste barrel and the radioactive activity measuring device for radioactive measurement, and move to the required measurement site according to the requirement. Through the control system, all running actions of the whole measuring device can be controlled, and the data collected by the dose measuring mechanism and the detector assembly are collected, the efficiency of the activity measurement of the radioactive waste barrel is improved, and the measurement operation of the low-activity radioactive waste barrel is conveniently and quickly completed.

The application relates to a kind of measuring device for measuring the alpha radioactivity activity concentration in spent fuel wastewater, comprising a support base, the top of the support base is provided with a liquid receiving tray, the outer side of one end of the liquid receiving tray is hung with a liquid inlet pump and a liquid outlet pump at intervals, and the outer side of the other end is hung with a sealed junction box; the liquid inlet pump is also connected with a constant liquid level pre-tank in communication through a pipeline; a support frame is arranged in the inner cavity of the liquid receiving tray, the top inner side of the support frame is fixedly connected with a liquid storage pool, the liquid storage pool is respectively connected with a first liquid level meter, a second liquid level meter and a third liquid level meter, and the bottom of the liquid storage pool is also connected with the liquid outlet pump in communication through a pipeline; the top outer side of the support frame is fixedly connected with a measuring pool, and the bottom of the measuring pool is connected with the top of the liquid storage pool in communication; the top of the measuring pool is provided with a film winding driving mechanism, a film is arranged on the film winding driving mechanism, and a detector is arranged on the top of the film winding driving mechanism. The application can effectively solve various problems of offline measurement, and realize online measurement of alpha activity concentration in high-concentration acidic liquid.

The utility model relates to an improved radioactive activity counting and lifting bucket which comprises a handheld transverse partition plate, a middle partition plate, a bottom support and a connecting rod, the handheld transverse partition plate is installed at the upper end of the connecting rod, the bottom support is installed at the lower end of the connecting rod, and the middle partition plate is installed in the middle of the connecting rod and located between the handheld transverse partition plate and the bottom support. The placing hole is positioned right above the bottom support; the improved radioactive activity counting and lifting bucket further comprises an injector positioning sleeve, the injector positioning sleeve comprises a supporting plate and a positioning sleeve, the upper end of the positioning sleeve is connected with the supporting plate, and a positioning opening communicated with the upper end of the positioning sleeve is formed in the supporting plate. The supporting plate is arranged on the middle partition plate, and the positioning sleeves are arranged on the inner sides of the containing holes in a sleeving mode. According to the improved radioactive activity counting and lifting bucket, the position of an injector containing radioactive liquid medicine on the middle partition plate can be more stable, the situation that the injector shakes or inclines is prevented, the medicine dosage measurement error can be effectively reduced, and radioactive medicine pollution is prevented.

The invention provides a radioactive activity meter which comprises a shell, the shell is of a composite structure, a shielding cylinder is detachably arranged in the shell, a containing cavity used for containing a glass container of radioactive medicine is formed in the shielding cylinder, a positioning clamping piece is arranged on the upper portion of the shielding cylinder, and a fixing frame is arranged on the outer side of the shell. An installation assembly is arranged on the fixing frame and comprises a connecting piece matched with the positioning clamping piece. According to the invention, rapid and efficient installation and positioning operation of the shielding cylinder can be realized through cooperation of the installation assembly and the positioning clamping piece, and efficient detection operation of particle activity of radiopharmaceuticals is greatly improved.

The present application relates to the technical field of system optimization, and discloses a method and system for performance collaborative optimization of multiple sets of separation systems based on federated learning, which comprises the following steps: obtaining the radioactivity value of the current batch of raw material liquid of each set of At-211 separation system, analyzing the radioactivity value based on a deep neural network, and generating a working condition sensitive feature vector representing the influence of different batches of radioactivity value on the performance of each separation system; through the working condition sensitive feature vectors, working condition attribute factors, activity working condition vectors and collaborative optimization coefficients generated in each step, the influence of different batches of radioactivity value can be accurately mined, the correlation and difference of each system working condition can be determined, the fine adjustment of differentiated aggregation weight can be realized, the distribution out-generalization failure of cross-activity migration can be avoided, the process parameters can be ensured to adapt to the demand of different activity raw material liquid, the collaborative ability of multiple sets of At-211 separation system can be improved, and the separation efficiency and product purity can be improved.

The invention relates to the technical field of radioactive source preparation, in particular to a preparation process of a 137Cs source for a blood irradiator. The process comprises the following steps: step 1, preparing raw materials: using 137Cs product liquid extracted from high-level liquid waste, wherein the radioactive activity of the 137Cs product liquid meets the basic requirements of a cesium source for a blood irradiator; step 2, cesium source pellet pressing: loading a 137Cs raw material into a mold, pressing a pellet in a hydraulic machine, and then drying and sintering at high temperature to obtain the cesium source pellet; and step 3, welding and sealing: the cesium source core block is arranged in a stainless steel source box, and the source box and the sleeve are sealed through an argon arc welding technology. The invention provides a process for purifying and transforming 137Cs product liquid extracted based on high-level liquid waste. A prepared radioactive source has the characteristics of high uniformity, high radioactive activity, small size, high difficulty, high sealing performance and the like; meanwhile, the 137Cs product liquid is successfully converted into the radioactive source meeting the standard of the blood irradiator, and autonomous preparation of the 137Cs source for the domestic blood irradiator is achieved.

The application discloses a method for estimating radioactivity concentration of desalinated water of a nuclear energy seawater desalination device, which comprises the following steps: firstly, according to the technological process of the nuclear energy thermal method seawater desalination device, the flowing direction of the medium and the migration direction of the radioactive substances are sorted out; then, according to the approach of the radioactive substances entering and removing in the intermediate loop fluid, the nuclide balance equation of the intermediate loop fluid is established, and then the radioactivity concentration calculation model of the intermediate loop water and the radioactivity concentration calculation model of the flash steam of the flash tank are obtained; then, according to the technological scheme of the MED device, the radioactivity concentration calculation model of the steam and the condensed water generated by each heat exchanger is established; then, the radioactivity level of the steam and the condensed water generated by each heat exchanger of the MED is calculated; finally, whether the desalinated water can meet the radioactivity control index is evaluated. The method can accurately calculate the radioactivity activity concentration of the desalinated water, and provides a reliable basis for the safety evaluation of the nuclear energy thermal method seawater desalination device.

The embodiment of the application provides a multifunctional food and water radioactivity detection device, wherein the multifunctional food and water radioactivity detection device has a radioactivity detection mode, and the multifunctional food and water radioactivity detection device comprises: a shielding main body; a Marin cup arranged in the shielding main body, the Marin cup being used for storing a sample to be detected; and a detection device, in the radioactivity detection mode, the detection device having a spectrum stabilization stage and a measurement stage, when the detection device is in the spectrum stabilization stage, the detection device is located outside the shielding main body, and when the detection device is in the measurement stage, at least part of the detection device is located in the Marin cup. The technical scheme of the embodiment of the application is characterized in that the detection device is located outside the shielding main body in the spectrum stabilization stage, and at least part of the detection device is located in the Marin cup in the measurement stage, so that in the radioactivity detection mode, a natural radioactive nuclide can be used for spectrum stabilization, thereby avoiding the adverse effect of the shielding main body on spectrum stabilization and ensuring the accuracy of the activity detection result.

A method for determining the position (zk) or radioactive activity of gamma ray sources (Pk) of an object, wherein: b) interaction data, or 'electron recoil's, are acquired with a Compton camera during movement of the object; c) these electron recoil's (REi) are grouped into groups (Gj) relative to the same gamma ray; e) for each group and each possible sequence (Sjk) of electron recoil's in the group, a Compton cone (CCjk) is constructed and its intersections (Pjkl) with the object's axis (z) are calculated; f) for each group, for each possible sequence (Sjk) of electron recoil's, a weighted fraction (Rjkl) of gamma ray emitted for each intersection is estimated; g) from the weighted fractions, a radiation curve (CR) representing the activity density of the sources is established; h) their position or activity is determined from the radiation curve. Figure for the summary: Figure 6A

The invention relates to the technical field of system optimization, and discloses a federated learning-based performance collaborative optimization method and system for multiple sets of separation systems, and the method comprises the steps: obtaining the radioactivity value of the current batch of raw material liquid of each set of At-211 separation system, and carrying out the analysis of the radioactivity value based on a deep neural network, generating a working condition sensitive feature vector representing the influence of different batches of radioactive activity values on the performance of each separation system; through the working condition sensitive feature vector, the working condition attribute factor, the activity working condition vector and the collaborative optimization coefficient which are sequentially generated in each step, the influence of different batches of radioactive activity values can be accurately mined, the working condition association and difference of each system are determined, the differential aggregation weight fine adjustment is realized, the out-of-distribution generalization failure of cross-activity migration is avoided, and the system safety is improved. It is ensured that technological parameters adapt to the requirements of raw material solutions with different activities, the cooperative capacity of multiple At-211 separation systems is improved, and the separation efficiency and the product purity are improved.

The application provides a method and system for real-time evaluation of adsorbent performance for radioactive gas treatment, and relates to the technical field of environmental monitoring. The method comprises the following steps: deploying a plurality of radioactivity sensors, temperature sensors and humidity sensors at different depths in the axial and radial directions of the adsorbent bed layer, collecting the radioactivity concentration, temperature and humidity at each position in real time through the sensors; and arranging ventilation impedance sensors and organic volatile sensors at the inlet and outlet of the adsorption unit and inside the bed layer, and synchronously collecting the ventilation impedance and the concentration of organic volatiles. The application realizes the global three-dimensional monitoring of the adsorption performance of the adsorbent, the accurate correction of multiple factors and the automatic discrimination of the safety threshold.

The invention belongs to the technical field of radiation monitoring, and particularly relates to a method for correcting the detection efficiency of I-129 in a radioactive iodine sampling carbon box, the specific distribution depth of radioactive substances can be obtained by measuring the counting rate of a to-be-detected activated carbon powder sample, and then the detection efficiency value at the depth is obtained through a function relation. The method is used for I-129 radioactive activity concentration calculation. And the detection efficiency of each carbon box sample after correction can be quickly obtained. According to the technical scheme, calculation of complex distribution parameters can be avoided, a correction value can be rapidly obtained from a curve for an actual sample through the constructed correction curve and function, accurate measurement of the I-129 radioactive activity concentration in the iodine sampling carbon box is achieved, an effective basis is provided for index emission control and atmospheric environment safety evaluation, and the method is suitable for industrial production. And the method still retains non-destructive analysis of the carbon box sample, and is simple to operate and high in timeliness.

This invention relates to the field of radiation monitoring technology and discloses a method and system for monitoring radioactive separation and leakage prevention based on multi-sensor data. The method includes: Step 1, dividing the monitoring area and establishing a step-by-step reference model; Step 2, performing background counting measurements and baseline initialization; Step 3, simultaneously acquiring radiation, liquid level, pressure, and accumulated liquid data, determining the net radiation measurement value, and generating a unified spatiotemporal state vector; Step 4, determining the abnormal quantity of the liquid path and the liquid event judgment result; Step 5, determining the actual normalized activity distribution ratio, activity migration distortion, and activity exceeding the prohibited zone boundary, obtaining the radioactive trajectory anomaly judgment result; Step 6, obtaining the system joint state and determining the priority anomaly source segment; Step 7, determining the total measured activity of the system, the radioactive activity loss judgment result, and the monitoring result. This invention achieves automatic monitoring and location of liquid anomalies, radioactive migration anomalies, and radioactive leakage risks.

The invention relates to a real-time monitoring device and method for beta radioactive activity in fluid, and the device is connected with a radioactive waste liquid decay pool through an extraction pump, and is used for extracting the fluid in the radioactive waste liquid decay pool; the solid scintillation cell is installed at the downstream of the draw-off pump, solid scintillation particles are placed in the solid scintillation cell, the solid scintillation cell is a quartz glass cavity, the scintillation particles are of a spherical structure with the particle size of 50-300 micrometers, and beta particles in the fluid emit scintillation light through the solid scintillation particles; the triple photomultiplier is arranged around the side wall of the solid scintillation cell and is used for capturing scintillation light from three directions and converting the scintillation light into three electric signals; and the coincidence counting module is connected with the triple photomultiplier and is used for receiving the three electric signals for coincidence counting and determining the beta radioactivity. The probability of interaction between the beta particles and the scintillation material is improved, synchronous detection of the triple photomultiplier is realized, the detection precision is improved, and online monitoring of the fluidity of fluid is realized.

The invention discloses a treatment method of 103Pd-containing alkaline radioactive waste liquid, and relates to the technical field of radioactive waste liquid treatment. The treatment method of the 103Pd-containing alkaline radioactive waste liquid comprises the following steps: S1, adding an oxidizing agent into the 103Pd-containing alkaline radioactive waste liquid for oxidation treatment to obtain a first mixed solution; s2, mixing the first mixed solution with a dichlorotetraammine palladium solution to obtain a second mixed solution, adding excessive reducing agent to fully react, and separating to obtain a treated solution and radioactive precipitates; and repeating the steps S1-S2 until the radioactive activity of the treatment solution is the same as that of the background. The treatment method provided by the invention is good in treatment effect, simple and high in operability, 103Pd in the alkaline radioactive waste liquid is converted into a solid, the radioactivity of the treated waste liquid is the same as that of a background, the treated waste liquid can be treated as common waste liquid, and the radioactive solid obtained after conversion is extremely small and is easier to store and decay.

The invention discloses an in-situ online monitoring method and system for radioactive substances in nuclear medicine waste liquid, and the method comprises the steps: directly placing a detector in decay pool radioactive waste liquid, transmitting an electrical signal to a data terminal through a signal line, and connecting an online monitoring data management platform through a 5G mobile communication network; a sodium iodide detector is selected, and the radioactive activity of iodine 131 is monitored by adopting an energy spectrum analysis method; the total alpha and total beta radioactivity is converted by measuring gamma ray activity accompanied by characteristic nuclide decay. The system comprises a detector, a data terminal, a 5G mobile communication network and an online monitoring data management platform. According to the invention, through in-situ monitoring and energy spectrum measurement, the monitoring analysis time is shortened, and the problem that direct measurement is difficult due to short range of alpha and beta rays in water is solved.

The invention provides a method for measuring carbon-14 in liquid effluent, and particularly relates to the technical field of radioactive waste monitoring. The measuring method comprises the following steps: pre-treating liquid effluent through a filtering device so as to remove particulate matters, colloids and suspended matters; the pretreated liquid effluent is injected into a combustion furnace with a catalyst, oxygen is introduced at the same time, and inorganic carbon and organic carbon in the liquid effluent are converted into carbon dioxide; carrying out gas-liquid separation on the oxidized gas through fan condensation and semiconductor condensation in sequence; adsorbing the carbon dioxide gas by using a molecular sieve, and measuring the residual gas which is not adsorbed by the molecular sieve through a non-dispersive infrared detector to obtain the carbon concentration in the residual gas which is adsorbed by the molecular sieve; carbon dioxide desorbed by the molecular sieve is introduced into a beta detector with plastic scintillation microspheres for radioactive activity measurement. A traditional alkali liquor absorption method is not needed, hazardous waste emission is reduced, and full-automatic measurement is achieved.

The invention relates to the technical field of nuclear radiation monitoring and informatization management, in particular to an informatization management method and system for radioactive aerosol samples, and the method comprises the steps: a cloud basic library construction process: presetting a nuclide decay constant library on a cloud management platform; an initial fingerprint anchoring process: acquiring an initial radioactive activity spectrogram and a first time stamp; constructing a dynamic decay calculation model through function mapping processing; a physical consistency judgment process: obtaining an actually measured radioactive activity value and a second time stamp; inputting a model to calculate and generate a theoretical activity residual value; calculating a numerical deviation to determine a confidence coefficient residual error; a result execution process: if the residual error is smaller than a preset verification threshold value, generating an archiving confirmation instruction; if yes, generating an abnormal alarm signal and locking the sample data; according to the invention, normal physical decay and artificial counterfeiting interference can be accurately distinguished, and the verification accuracy is extremely high.

The present application relates to the technical field of radioactive waste water treatment, and discloses a method for discharging radioactive waste water of a nuclear medicine department up to standard, which adopts a system comprising a temporary storage pool, a waste water pool, a purified water pool and a non-contact membrane distillation device. The method comprises the following steps which are cyclically executed according to a treatment period: radioactive waste water generated by the nuclear medicine department and concentrated liquid generated during operation of the non-contact membrane distillation device are both discharged into the temporary storage pool and mixed and temporarily stored. When the non-contact membrane distillation device stops operating, the waste water temporarily stored in the temporary storage pool is transferred to the waste water pool. Subsequently, the non-contact membrane distillation device is started, and the waste water in the waste water pool is purified, and the purified liquid is discharged into the purified water pool. The purified liquid is stored and decayed in the purified water pool, and is discharged after the radioactivity reaches a preset discharge standard. The present application can shorten the total time required to reach the standard, and greatly reduce the volume requirement and land area requirement of a large decay pool.

1. Name of the product in this design: Radiation Particle Counter. 2. Application of this design: It is used in fields such as nuclear power plants, nuclear chemical industry and environmental monitoring to perform four-channel simultaneous measurement and radioactivity analysis of α and β radiation particles in collected gaseous and liquid samples. 3. The key design feature of this product is its shape. 4. The image or photograph that best illustrates the design's key points: a 3D model. 5. The bottom surface of this product is a part that is not easily seen or cannot be seen during use, so the bottom view is omitted.

The invention relates to the technical field of column efficiency evaluation, and discloses an imidazolium resin column efficiency dynamic evaluation method and system for At-211 online separation, and the method comprises the following steps: in the At-211 continuous separation process, collecting the bed height value of an imidazolium resin column, the pH value of an effluent and the radioactivity of At-211 in an eluent in real time; a bed height value, an effluent pH value and eluent radioactivity are collected in real time, a swelling disturbance index and a peak shape broadening coefficient are obtained through calculation in sequence, a column efficiency fluctuation factor and a passivation influence factor are obtained through collaborative analysis, and finally a health degree index is generated. Reversible fluctuation and irreversible attenuation of the column efficiency are clearly distinguished, the in-column self-recovery capability and the irreversible degradation accumulation degree are reflected, and the accuracy and comprehensiveness of dynamic evaluation of the column efficiency are improved.

This invention relates to the interdisciplinary field of nuclear reactor engineering and corrosion engineering, and in particular to an online measurement device for fouling on the surface of fuel cladding tubes based on radioactive isotope tracing, comprising: an injection control module for injecting radioactive... 59 Fe solution was added to the coolant, and the effect of Fe ion concentration on the coolant was analyzed. 59 Fe content is regulated and controlled; experimental module for use based on injected radioactivity. 59 The Fe solution coolant was used to test the fuel cladding surface; a measurement module was used to collect data on the scale that formed on the fuel cladding surface after the test. 59 Fe radioactivity is used to estimate the surface density of the deposited scale. This invention controls the amount of Fe in the coolant... 59 The Fe content, and its effect on the scale buildup on the fuel cladding surface. 59 Online detection of Fe radioactivity can accurately calculate the corresponding 59 The Fe mass is used to infer the scale mass, and the scale information on the surface of the cladding tube is obtained in real time to reflect the dynamic changes of scale in a timely manner.

This invention relates to a method for controlling the activity ratio of terbium-160 to terbium-161 in the preparation of terbium-161, comprising: S1, placing a natural Gd target or a high-abundance 160Gd or 158Gd target in a reactor for irradiation, then removing and cooling the target, dissolving the Gd target, analyzing the radioactivity of 161Tb ATb-161 and 159Gd AGd-159 in the solution, and calculating the nuclear reaction rates Øthermal σGd-160 and Øthermal σGd-158; S2: Place the natural Tb target in the reactor for irradiation, then remove and cool it. Dissolve the natural Tb target and analyze the radioactivity of 160Tb in the solution (ATb-160). Calculate the nuclear reaction rate Øthermal σTb-159. S3: Based on the nuclear reaction rate data obtained in S1 and S2, calculate the relationship between the irradiation time of a high-abundance 160Gd (greater than 90%) target (containing 158Gd and 159Tb impurities) and the 160Tb / 161Tb activity ratio generated.

The invention relates to the technical field of radiation monitoring, and discloses a radioactive separation liquid leakage prevention monitoring method and system based on multi-sensor data, and the method comprises the steps: 1, dividing a monitoring region, and building a step reference model; 2, background counting measurement and baseline initialization are carried out; 3, radiation, liquid level, pressure and hydrops data are collected synchronously, net radiation measured values are determined, and time-space unified state vectors are generated; 4, determining a liquid path abnormal quantity and a liquid event judgment result; 5, determining an actual normalized activity distribution proportion, an activity migration distortion amount and a forbidden area activity cross-border amount, and obtaining a radioactive trajectory anomaly judgment result; step 6, obtaining a system joint state and determining a priority abnormal source segment; and step 7, determining total measured activity of the system, a radioactive activity loss determination result and a monitoring result. According to the invention, automatic monitoring and positioning of liquid abnormity, radioactive migration abnormity and radioactive leakage risks are realized.