329 results about "Nuclear facilities" patented technology

The invention relates to the technical field of nuclear facility decontamination, and provides a multiphase carbon dioxide decontamination recovery system and a decontamination recovery process, the decontamination recovery system comprises a dry ice supply loop, a high pressure CO2 supply loop, a decontamination loop and a CO2 recovery loop; the tail ends of the dry ice supply loop and the high-pressure CO2 supply loop are communicated with the decontamination loop; the tail end of the decontamination loop is communicated with the CO2 recovery loop; the decontamination recovery process comprises the following steps: taking ethanol or acetone as an entrainer, dissolving a decontaminating agent by using supercritical carbon dioxide to carry out soaking decontamination pretreatment on the radioactive contamination surface, taking high-pressure carbon dioxide as power, carrying dry ice particles and spraying out from a high-pressure spraying pipe to impact the radioactive contamination surface, and recycling the radioactive contamination surface. Recycling of carbon dioxide is realized through two-stage depressurization separation and first-stage filtration; the carbon dioxide radioactive decontamination capability and efficiency can be remarkably improved, the secondary waste generation amount is reduced, and the personnel irradiation risk is reduced.

The invention provides a nuclear radiation diffusion analysis method based on a Gaussian mixture atmospheric diffusion model. The method comprises the steps that nuclear facility source item parameters are acquired; integrating meteorological, geography, remote sensing and radiation monitoring data by using a heterogeneous data fusion engine, extracting atmospheric turbulence, terrain and building interference characteristics and source item parameters, and forming a dynamic input parameter set; constructing an unsteady state diffusion model containing a multi-modal distribution function, processing features, obtaining a mixed distribution model, and correcting the mixed distribution model; predicting spatial and temporal distribution of radiation pollutants, and generating multi-scale diffusion field simulation; and optimizing a diffusion path, and generating a three-dimensional risk field. According to the method, multi-source data are integrated, an unsteady state diffusion model is constructed, Gaussian component weights are dynamically adjusted, the model is corrected by using real-time data, and a geographic information system is coupled to carry out spatial constraint optimization. And through multi-scale feature coupling, dynamic parameter adjustment and geographic space constraint correction, the depicting capability of the atmospheric diffusion model is remarkably improved, and the nuclear radiation diffusion prediction precision is greatly improved.

The invention provides a nuclear facility aerosol nuclide activity monitoring device, which comprises a detector shell, the outer wall of the detector shell is provided with a detector interface, an air inlet pipe interface and an exhaust pipe interface, the air inlet pipe interface is outwards connected with an air inlet pipeline, and the exhaust pipe interface is outwards connected with an exhaust pipeline; the radiation detector is connected to the detector interface; the paper feeding mechanism is arranged in the detector shell and comprises filter paper which extends between the detection end of the radiation detector and the air inlet pipe connector; the output end of the moving assembly is connected with the filter paper; the shielding body assembly comprises an external shielding body and an internal shielding body, the radiation detector is sleeved with the external shielding body, the internal shielding body is arranged in the detector shell, and the filter paper is located between the detection end of the radiation detector and the internal shielding body. According to the invention, the change condition of the activity concentration of the aerosol radionuclide in the airborne effluent can be obtained in time.

The invention discloses a nuclear facility decommissioning simulation file editing management method based on cloud and local collaboration, and relates to the technical field of file management, and the method comprises the steps: verifying the identity of a user, receiving a file, and converting the file format; processing the simulation file through the first collaborative editing and performing real-time auditing; and setting a file operation authority based on the first encrypted storage file. According to the nuclear facility decommissioning simulation file editing management method based on cloud and local collaboration provided by the invention, intermediate format conversion is performed after the data is received, the applicability and flexibility of the system are improved, and the efficiency of multi-user operation is improved through a collaborative editing and auditing mechanism; and meanwhile, the correctness and consistency of the file are ensured in the aspect of processing conflicts, the security of the data is protected through encrypted storage and authority control, and higher security and recovery speed are achieved in the face of attack and decryption. The method has better effects in the aspects of safety, application range and reliability.

The invention relates to a shot blasting particle internal circulation regeneration method for decontaminating radioactive contaminated metal, which is applied to a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The invention discloses a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The shot blasting particle internal circulation regeneration system comprises a smelting furnace, a melting and pumping machine and a shot blasting machine which are sequentially used according to a closed-loop sequence, the method comprises the following steps: raw material pretreatment; smelting and decontaminating the raw materials; preparing pills by a melt extraction machine; shot-blasting and decontaminating the raw materials; and after decontamination, smelting and pelleting. The method has the advantages that radioactive contamination metal is converted into self-consumption shot blasting particles, cyclic regeneration is achieved, radioactive waste increment is remarkably reduced, near-zero emission of nuclear facility decommissioning waste is promoted, and the requirement for minimization of IAEA radioactive waste is met.

The invention relates to a nuclear facility radiation field model construction method and a dose evaluation system, and the system is configured to establish a three-dimensional space coordinate system, construct a three-dimensional radiation field model based on radiation field data and radiation source data, and correct the radiation field model at the current moment according to the radiation source data, introducing an attenuation coefficient of the three-dimensional nuclear facility on the original three-dimensional scene model to correct the three-dimensional scene model; correcting the radiation field model based on the corrected three-dimensional scene model; calling the three-dimensional scene model and the radiation field model according to an operation path selected by a user; and simulating the space range of each organ of the human body sweeping along with the movement of the human body in the working path in the three-dimensional scene model, obtaining the time of each organ staying on the path of the unit space, and calculating the real-time dose received by the human organ according to the radiation dose rate in the unit space. According to the invention, the change of the radiation field caused by the disassembly and assembly of the nuclear facility can be corrected, and the optimization of radiation protection is realized.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

The invention discloses a method and a device for calculating the concentration of gaseous tritium discharged by a nuclear facility and an evaluation method and a device. The method comprises the following steps: acquiring meteorological data, environmental parameters and discharge parameters of the nuclear facility; determining an atmospheric dispersion factor of gaseous tritium discharged by the nuclear facility based on the meteorological data, the environmental parameters and the discharge parameters; determining a re-evaporation factor of the discharged gaseous tritium based on the atmospheric dispersion factor, the deposition property of the gaseous tritium, meteorological data and environmental parameters; determining a reevaporation dispersion factor of gaseous tritium based on the meteorological data, the environmental parameters and the reevaporation factor; and adding the atmospheric dispersion factor and the reevaporation dispersion factor to obtain the concentration of the gaseous tritium discharged by the nuclear facility. The method can accurately evaluate the concentration of gaseous tritium in the surrounding environment after the nuclear facility discharges gaseous tritium.

The invention relates to a method for evaluating the radiation dose of special public nearby a nuclear facility, and the method comprises the steps: estimating the concentration distribution of radionuclides in air, surface soil and a biological medium nearby the nuclear facility through collecting the radiation dose evaluation parameters of a target special public and combining an environment quality evaluation model; based on the data, the annual effective dose of the target special public at the nuclear facility boundary and the living quarter is calculated, and a plurality of ways such as inhalation internal irradiation, air immersion external irradiation, surface deposition external irradiation and ingestion internal irradiation are considered. In addition, a dynamic calculation method is also introduced, especially for the influence of year-by-year change of the cumulant of radionuclides deposited on the earth surface, factors such as decay, resuspension and infiltration into underground water of nuclides are fully considered, and the accuracy and foresight of evaluation are improved. Accurate and comprehensive technical support is provided for radiation protection of the special public around the nuclear facility, and the requirements of the nuclear facility public for dose monitoring and risk management are met.

The invention provides a multi-nuclide automatic separation and detection system and method, and particularly relates to the technical field of radioactive substance detection. The detection system comprises a cascade separation and regeneration unit, a dynamic regulation and control unit, an online detection unit, an eluent conveying unit and a control system, and the eluent conveying unit is matched with the cascade separation and regeneration unit to separate and purify radionuclide and regenerate resin. The dynamic regulation and control unit is used for controlling a flow path between the eluent conveying unit and the cascade separation regeneration unit and feeding back changes of pressure, temperature and pH value in the flow path in real time, and the online detection unit is used for detecting concentration of nuclides in separation liquid and feeding back monitoring data to the control system. And the control system controls the operation of each functional unit and automatically plans a separation path according to a measurement requirement to form a separation-detection-optimization closed-loop process. The device is suitable for the fields of nuclear facility liquid effluent detection, environmental water radioactivity detection and the like, and has high efficiency, environmental protection property and intelligence.

The invention discloses an edge computing gateway system based on radiation monitoring equipment, and belongs to the field of radiation monitoring, the edge computing gateway system comprises the radiation monitoring equipment, an edge computing gateway and a cloud Internet of Things platform which are connected in sequence, and the edge computing gateway is connected with the cloud Internet of Things platform through an MQTT protocol; the edge computing gateway mainly comprises a dual-architecture processor, a protocol library plug-in, an edge computing engine, an offline data storage module and a device configuration module. The system is dynamically compatible with a multi-source heterogeneous protocol, supports Internet of Things platform standard communication, simplifies configuration management, realizes local edge calculation, provides abnormal data discrimination and other functions, and solves the problems of poor protocol compatibility, insufficient data reliability, complex configuration management, lack of intellectualization, weak support of mobile equipment and the like in the prior art. The system is especially suitable for monitoring and management of radiation environments such as nuclear facilities, hospitals and industrial flaw detection.

To dismantle a nuclear facility affected by a severe accident in an underwater environment by submerging the facility in water so that the water shields radiation from the nuclear facility.SOLUTION: The method for dismantling a nuclear facility includes: stopping water leakage at a leakage portion by using a particle dispersion liquid containing fine particles having a specific gravity greater than that of water, when dismantling a nuclear facility in which the water leakage portion has occurred due to a severe accident; and submerging at least a part of the nuclear facility. This makes it possible to submerge a reactor well and to perform dismantling work from above a reactor building.SELECTED DRAWING: Figure 1

The invention provides a method, a device and equipment for determining a decontamination path of a radioactive substance contaminated metal plate, and relates to the technical field of nuclear facility decommissioning governance, and the method comprises the steps: obtaining a metal plate image; dividing the metal plate image into a plurality of detection areas; radioactive substance pollution detection is carried out on the multiple detection areas, and area pollution values are determined; determining a polluted area according to the area pollution value; and determining a decontamination path of the radioactive substance polluted metal plate according to the polluted area. According to the scheme, the decontamination sequence and the decontamination times of all the detection subareas are designed, the decontamination track is planned, pertinence is better achieved, the pollution level of the plate metal can be rapidly reduced, and the decontamination efficiency is effectively improved.

The utility model discloses a cleaning isolation cabin for installing a modular integrated reactor. The cleaning isolation cabin comprises a main cabin body, a movable ceiling, a bearing base, air purification equipment, an electric control box body, an air shower, an illuminating lamp and a monitoring camera, the main cabin body is mounted on the bearing base, the upper end of the main cabin body is opened to form a hoisting opening, and the movable ceiling is correspondingly and horizontally arranged on the hoisting opening; an isolation cabin access port communicated with the outside is formed in the circumferential direction of the main cabin body, the air shower is correspondingly arranged on the outer side of the isolation cabin access port, and an outlet of the air shower is communicated with the isolation cabin access port; the air purification equipment is communicated with the interior of the main cabin body, the electric control box body is arranged on the inner peripheral wall of the main cabin body, and the illuminating lamp and the monitoring camera are arranged at the top of the inner peripheral wall of the main cabin body. The clean isolation cabin has the advantages that repeated investment can be reduced, large-range isolation space is avoided, manpower and material resource investment can be reduced, the construction period of nuclear facility engineering is shortened, and economic efficiency is improved.

The invention relates to the technical field of compressed air system intelligent control, and discloses an intelligent control and air supply distribution method and system for a nuclear facility compressed air system pipe network. Carrying out numerical simulation on the distributed arrangement and operation conditions of different air compression stations and the flow and pressure characteristics of the compressed air pipe network under the intermittent load of different process equipment; on the basis of data generated by numerical simulation, the pipe network tail end pressure of the compressed air pipe network system is adjusted through an intelligent fuzzy self-tuning PID control method, and the operation state of an air compressor unit of the compressed air pipe network system is optimized on the basis of a flow matching strategy; pipe network operation parameters of the compressed air pipe network system are collected in real time, and the control strategy is fed back and adjusted. The whole compressed air system can operate efficiently and stably, the requirements of all links of nuclear facilities for compressed air are guaranteed, meanwhile, the operation intelligence and reliability of the system are improved, and adverse effects caused by unstable pressure and the like are reduced.

The invention discloses a nuclear facility decommissioning simulation cloud model intelligent processing and rendering method and system, and relates to the technical field of computer graphic processing and three-dimensional model rendering, and the method comprises the steps: uploading a first model file, and carrying out the first analysis; processing the first model data for serialized storage; and loading the first model and carrying out scene real-time rendering. According to the intelligent processing and rendering method for the nuclear facility decommissioning simulation cloud model, system resources are effectively distributed through an asynchronous parallel processing mechanism, and blockage of a main thread is avoided. The compatibility of the multi-format model is realized by calling the plurality of model analysis sub-modules, and the efficiency and accuracy of processing different-format models by the system are improved. The compatibility of the multi-format model is realized by calling the plurality of model analysis sub-modules, and the efficiency and accuracy of processing different-format models by the system are improved. The method has better effects in the aspects of stability, model processing efficiency and accuracy.

The invention discloses a parameter optimization method and system based on an agent model and multi-algorithm gradient collaboration, and relates to the technical field of nuclear engineering and nuclear security, and the method comprises the steps: firstly determining a nuclear facility parameter combination, carrying out the high-fidelity calculation through a Monte Carlo program to obtain a Keff value, and constructing a training set; training a micro-proxy model capable of predicting a Keff value and gradient information through a feedforward neural network in combination with a back propagation algorithm, taking the micro-proxy model as a target function, taking the minimum absolute error of a Keff predicted value and a target value as an optimization target, and generating candidate parameter solutions through global exploration of a hybrid optimization algorithm; and an optimal parameter combination candidate solution is obtained through gradient-assisted local optimization, and finally, through Monte Carlo program verification, if the error reaches the standard, the optimal parameter combination candidate solution is used as a final parameter combination solution. The problem that a parameter optimization method in the prior art cannot give consideration to calculation efficiency and precision is solved.

To provide a plant reliability evaluation system capable of improving the reliability of equipment including not only conventional equipment but also large structures such as structural materials and weld lines. by simultaneously utilizing in-service inspections and operating parameters of nuclear facilities in a plant.SOLUTION: A plant reliability evaluation system S comprises: a corrosion potential sensor 4; a first water quality measuring unit; a dose rate monitor; a detection unit 511 for taking these pieces of measurement data as environment information of a plant during operation; a storage unit for storing a material composition forming a nuclear reactor, deterioration data of the material, and inspection results; a soundness monitoring unit 514 for always monitoring soundness of equipment forming the plant, on the basis of environment information of the plant during operation, the environment information not being taken in reliability evaluation of equipment regulated by the Institute of Nuclear Power Operations in the United States; and a life cycle management unit 516 for planning a repair plan for the plant on the basis of the soundness evaluation result, and performing life cycle management.SELECTED DRAWING: Figure 6

The invention belongs to the technical field of robot teleoperation and haptic interaction, and provides a multi-mode force feedback control method and system for nuclear facility robot operation, and the method comprises the steps: collecting the state information of a master arm and a slave arm in real time, and dynamically scheduling a haptic calculation strategy according to a task state; a fast estimation strategy is enabled in the fast transit mode. Further, real environment interaction force is obtained based on dynamic model compensation and net interaction force extraction; combining the dynamically selected multi-mode force feedback parameters, and synthesizing and outputting a touch instruction to the main arm. Meanwhile, admittance correction and feed-forward compensation are carried out on a slave arm motion instruction through net interaction force and dynamic internal force, synchronous output is carried out after safety optimization, and the slave arm is controlled to move. The problems of poor task adaptability, force sense distortion and insufficient safety in nuclear facility teleoperation are solved, and intelligent, high-fidelity and safe robot teleoperation is achieved.

The embodiment of the invention provides a nuclear facility decommissioning project three-dimensional waste cutting and boxing collaborative simulation method and system. The method comprises the steps of obtaining three-dimensional model data, waste storage container data and cutting constraint data of a target nuclear facility; performing format conversion on the three-dimensional model data and the waste storage container data to generate target three-dimensional data and target container data; based on a preset optimization engine, the target three-dimensional data, the target container data and the cutting constraint data, cutting and boxing co-simulation is carried out, and a simulation scheme is generated; optimizing the simulation scheme based on preset optimization parameters, and generating a Pareto frontier solution set; in response to selection of a user in the Pareto frontier solution set, determining a final selection result; and generating a cutting and boxing simulation project report based on the final selection result. In this way, the waste can be flexibly and efficiently treated.

The invention relates to the technical field of nuclear facility decommissioning robots, and discloses a nuclear decommissioning robot based on laser cutting technology teleoperation, which comprises a supporting seat, a mechanical arm assembly, a visual sensor and a laser cutting head. A crawler belt is arranged at the bottom of the supporting base and used for moving and positioning the robot. The mechanical arm assembly comprises a main arm, a supporting arm, a short arm and an end effector, and precise operation is achieved through cooperation of a multi-stage motor and an air cylinder. The visual sensor comprises a radiation sensor, a force feedback sensor and a temperature sensor and is used for monitoring environmental parameters and operation states in real time. The laser cutting head is provided with a focus lens, a cooling system and an energy regulator, and heat dissipation is achieved through a cooling liquid circulating pipe. The control system comprises a wireless communication module, a control unit, an image processing unit and a camera, and remote operation and real-time monitoring are achieved. According to the invention, the safety, flexibility and efficiency of nuclear decommissioning work are improved.

The invention discloses an electrochemical denucleation decommissioning facility oxide layer method based on a synergistic acidic electrolyte, and relates to the technical field of cleaning. The method comprises the following steps: by taking a polluted metal component as an anode and an inert electrode as a cathode, immersing the polluted metal component into a synergistic acidic electrolyte of a low-concentration acidic medium, and stripping an oxide layer on the surface of the polluted metal component until a clear grain boundary is exposed at the temperature of lower than 40 DEG C in a high-voltage direct-current electrolysis mode. By developing a synergistic enhanced acidic electrolyte system, high decontamination rate is realized in a low-concentration sulfuric acid medium, radionuclide stripping is accurately controlled to avoid matrix pitting corrosion damage, and high-valence nuclides in a compact oxide layer are deeply removed, so that the decontamination efficiency is improved. Finally, an efficient, low-damage and stable-process radioactive contamination metal treatment scheme is provided for nuclear facility decommissioning engineering. The method is suitable for removing radioactive contamination oxidation layers on the surfaces of the inner walls of stainless steel pipelines and reactor containers in nuclear facility decommissioning projects, and radionuclides are enriched in the oxidation layers.

The invention discloses a preparation method of a starch-based gel color developing material for visual detection of airborne iodine nuclides, which comprises the following steps: adding starch, a polymer matrix material and a plasticizer into deionized water for soaking and uniformly stirring to obtain a starch-based gel matrix solution; placing the starch-based gel matrix solution at a certain temperature, and stirring to obtain gel paste; and injecting the gel paste liquid into a mold, and carrying out freeze-thaw cycle to obtain the starch-based gel color developing material for airborne iodine nuclide visual detection. The starch-based gel color developing material has the characteristics of quick response, stable color development and lasting color and luster for airborne iodine nuclide at normal temperature, has excellent mechanical strength, machinability and recycling performance, can be flexibly processed into forms such as a film and a test piece, or can be integrated in various detection devices, and has a wide application prospect. The method is suitable for places needing airborne iodine nuclide detection, such as nuclear medicine laboratories, nuclear facilities / nuclear equipment and the like, and meets the requirements of real-time visual detection and early warning.

The invention relates to the technical field of super-structure lens design, and provides an infrared detection device based on a super-structure lens, a design method and a use method thereof, which can be suitable for extreme environments such as high radiation and lay a solid foundation for research on thermal infrared imaging leakage detection equipment which is miniaturized, has high performance and is suitable for nuclear facility environments.

The invention discloses an anti-leakage intelligent monitoring double-layer casing pipe, assembling equipment and an assembling method thereof, and relates to the technical field of nuclear facility or chemical equipment matching, the anti-leakage intelligent monitoring double-layer casing pipe comprises an inner pipe and an outer pipe, the outer pipe is arranged on the outer side of the inner pipe in a sleeving mode, and multiple sets of supporting rings are arranged between the inner pipe and the outer pipe at equal intervals; the multiple sets of supporting rings are connected with the inner pipe. A monitoring device is arranged on one side of the outer pipe and used for monitoring leakage of the inner pipe. The assembling equipment comprises a supporting and guiding assembly, a welding assembly, an inner pipe milling cutter, an inner pipe ironing plate, an outer pipe milling cutter and an outer pipe ironing plate. The assembling method comprises the steps of preparation, inner pipe butt joint and appearance butt joint. A single safety barrier is upgraded into a double-independent safety barrier by arranging a double-layer sleeve structure formed by combining the inner pipe and the outer pipe.

The invention relates to the technical field of nuclear facility pipeline heating. The invention provides a pipeline heating device and an in-reactor test facility. The pipeline heating device comprises a magnetic conduction layer, a heat conduction layer, a heat preservation layer and an electromagnetic induction coil, the magnetic conduction layer is made of a magnetic alloy material, and the magnetic conduction layer is enclosed and internally forms a heating area used for containing a pipeline; the heat conduction layer is located on the side, facing the heating area, of the magnetic conduction layer and used for transmitting heat of the magnetic conduction layer to the pipeline. The heat preservation layer wraps the side, away from the heating area, of the magnetic conduction layer. The electromagnetic induction coil is wound around the side, away from the heating area, of the heat preservation layer. The magnetic conductive layer made of the magnetic alloy material serves as a main absorption and conversion carrier of magnetic field energy, the eddy current effect can be remarkably enhanced, the problem that the heating efficiency is insufficient due to low magnetic conductivity of the austenitic stainless steel pipeline is solved, and the heating efficiency is greatly improved. The arrangement of the magnetic conductive layer can fundamentally avoid material microscopic damage caused by direct action of a magnetic field, and the safety is higher.

The invention provides a combined automatic treatment system and method for tritium and carbon-14 in gaseous effluent, and particularly relates to the technical field of nuclear facility gaseous effluent monitoring. The treatment system comprises a gas inlet unit, a catalytic oxidation unit, a tritium trapping unit, a carbon trapping unit and a circuit control unit, a gas inlet of the catalytic oxidation unit is communicated with the gas inlet unit, and the catalytic oxidation unit is used for converting tritium gas and organic tritium in gaseous effluent into tritiated water vapor and converting organic carbon into carbon dioxide; the tritium trapping unit is communicated with a gas outlet of the catalytic oxidation unit, and can be used for condensing tritiated water vapor into liquid water and automatically sampling and detecting; the carbon capture unit comprises a neutralizer and a carbon dioxide sensor, a NaOH solution for absorbing carbon dioxide is arranged in the neutralizer, and the carbon dioxide sensor detects the absorption efficiency of carbon dioxide in real time; and the circuit control unit controls the operation of each unit. According to the system, catalytic oxidation, tritium condensation and carbon absorption are integrated, and synchronous treatment and monitoring of tritium and carbon-14 can be achieved.

A nuclear installation comprising at least one modular nuclear reactor (SMR) and a reactor vessel well delimiting a water basin in which the SMR reactor unit is immersed. The invention relates to a nuclear installation comprising: at least one SMR reactor unit (4) for heat generation, delimited by a reactor vessel (40, 41, 42); a reactor vessel well (100) delimiting a water-filled basin (B) forming part of a secondary circuit, in which the reactor vessel is immersed; at least one heat exchanger (49) between the primary circuit of the SMR reactor and the secondary circuit, arranged outside the reactor vessel and in the water basin. Figure for the abstract: Fig. 6

The invention relates to the technical field of neutron measurement, and particularly discloses a multi-activation foil and method for measuring a neutron energy spectrum. The multi-activation foil comprises a shell and an activation sheet placed in the shell, and the activation sheet sequentially comprises Ni, Sc, Au, W, Cu, Pt, In, Zn and Fe from top to bottom. The activated foil can realize high-resolution measurement of a neutron spectrum in a very small space, has the characteristics of size miniaturization, wide energy response range, wide neutron fluence rate application range, controllable manufacturing tolerance, optimized material ratio and the like, and is suitable for neutron spectrum and neutron dose measurement of a small-scale region of a nuclear facility and neutron dose measurement of a small-scale region of a nuclear facility. The method can also be popularized and applied to fine dose field distribution measurement of a large-scale area of a nuclear facility, and provides accurate data support for safe operation, shielding verification and radiation protection of the nuclear facility.

The invention discloses a liquid-phase deuterium-doped anti-radiation optical fiber, a preparation method and application, and belongs to the technical field of manufacturing of anti-radiation optical fibers. According to the method, deuterium is stably doped into a fiber core in the form of OD groups in the preparation stage of the optical fiber preform through an improved chemical vapor deposition combined solution doping technology, so that the problems that gas is easy to leak and the radiation resistance is attenuated along with time in a traditional gas loading technology are solved. The preparation process comprises the steps of pretreatment of the deposition tube, preparation of the barrier layer and the porous loose layer, solution soaking OD group doping, sintering collapse and wire drawing treatment. An OD group can be detected in the prepared optical fiber, the radiation resistance of the optical fiber is remarkably improved, after the optical fiber is irradiated by gamma rays with the total dose of 200Gy (Si), the radiation-induced attenuation is remarkably lower than that of a common optical fiber without the OD group, and a material basis is provided for long-term reliable application of the optical fiber in radiation environments such as space exploration and nuclear facilities.