31 results about "Nucleate boiling" patented technology

The invention discloses a heating furnace energy efficiency optimization method and system, and particularly relates to the technical field of operation control. The method comprises the following steps: acquiring boiling state parameters and structural deformation parameters of a water jacket heater in an operation process, identifying a critical point position of conversion from nuclear boiling to membrane boiling and membrane boiling duration, and calculating a thermal expansion displacement rate and an oscillation phase angle of a furnace shell; a heat transfer coefficient fluctuation compensation factor is generated by analyzing the phase lag relation between boiling phase change circulation and thermal expansion deformation; calculating a heat flow distribution adjustment amount according to the heat transfer coefficient fluctuation compensation factor; calculating a dynamic compensation correction coefficient by combining the flow velocity variable quantity of the cooling water and the flow-thermal expansion transfer function; based on the heat flow distribution adjustment amount and the dynamic compensation correction coefficient, the power output and the cooling water flow of the water jacket heating furnace are regulated and controlled, dynamic optimization adjustment of the heat transfer behavior of the heating furnace is achieved, and the energy efficiency stability and the heat transfer control precision of the water jacket heating furnace under complex working conditions are effectively improved.

A two-phase immersion cooling system for integrated circuit assemblies may be formed utilizing a heat dissipation device thermally coupled to at least one integrated circuit device, wherein the heat dissipation device includes at least one surface and at least one projection extending from the at least one surface, wherein the at least one projection includes at least one sidewall, and wherein the at least one sidewall of the at least one projection includes at least one surface area enhancement structure. Utilizing such a heat dissipation device can boost nucleate boiling, improve boiling performance, reduce superheat required to initiate boiling, boost the critical heat flux during boiling, and can translate to a greater number of integrated circuit devices / packages that can be placed into a single immersion cooling system.

The invention relates to an immersed liquid cooling device and method, and relates to the technical field of thermal management and electronic cooling. Comprising a closed cavity, an electronic element, a phase change material layer and a condensation piece, the closed cavity is filled with dielectric cooling liquid, the phase change material layer is loaded on the surface of the electronic element, and the superheat degree needed by bubble nucleation is remarkably reduced through the combined action of heat absorption and phase change of the phase change layer; a large number of effective nucleation sites are formed on the heating surface, so that bubbles are generated more easily, bubble merging is reduced, and bubble separation and updating are promoted; the phase change material layer maintains more stable nucleate boiling under medium-high heat flow, the porous structure not only can improve the average heat transfer coefficient, but also can absorb cold fluid through the capillary force effect to form heat convection to delay local dry spot formation, higher boiling heat exchange intensity is achieved, and boiling enhancement and heat flux density improvement are achieved.

The application relates to a method and device for determining a thermal margin of a nuclear reactor, a computer device and a medium, and relates to the field of nuclear engineering.The method comprises the following steps: determining a first predicted deviation of bubble nucleate boiling ratio of a to-be-detected reactor, wherein the first predicted deviation of bubble nucleate boiling ratio refers to a minimum predicted deviation of bubble nucleate boiling ratio of the to-be-detected reactor; determining a reactor parameter of the to-be-detected reactor at a predicted time corresponding to the first predicted deviation of bubble nucleate boiling ratio, wherein the reactor parameter comprises an axial power distribution of at least one reactor component in the to-be-detected reactor and a total power of the component, and the total power of the component refers to a sum of the axial power and the radial power of the reactor component; and determining the thermal margin of the to-be-detected reactor according to the reactor parameter.The application can improve the accuracy of the thermal margin of the nuclear reactor, and can more accurately reflect the actual situation of the to-be-detected reactor.

The invention provides a PGU-LCOS chip and light source co-packaging thermoelectric collaborative management system, which is characterized in that thermal visual features are extracted through infrared thermal imaging and SIFT and Mask R-CNN algorithms, a thermal similarity index is calculated, and a heat transfer state is divided into a single-phase convection area, a nucleate boiling area and a critical heat flux area according to TSI; a competitive model of the TEC refrigeration capacity and system thermal inertia is constructed, and the optimal refrigeration boundary is determined online; dynamically adjusting the TEC current by adopting PID and a feedforward acceleration compensation algorithm; a hierarchical self-adaptive micro-channel is generated by combining TSI hot spot information through Voronoi and a Gaussian flux model, and directional liquid cooling is achieved; a diamond cooling fin, nano-silver sintering paste and a fine polishing cold end are arranged on a chip-TEC interface to reduce thermal resistance; dynamically distributing the power of the TEC and the liquid cooling pump based on the heat flux residual ratio; and moisture condensation is inhibited through cold end micro-heating and a hydrophobic coating. According to the cooperative scheme, temperature precision, quick response and high reliability can be achieved, and the thermal management requirement of ultrathin and miniaturized projection display is met.

A cooling device includes an enclosure housing, a primary cooling system including a loop heat pipe like (LHPL) device that rejects heat to an external coolant. The LHPL device including an evaporator module, condenser module, vapor line, liquid return path including a liquid return line, one or more compensation chambers, optional inline storage chambers, a working fluid having a liquid and vapor phase and an optional pump in either the vapor or the liquid return line. The evaporator module including a porous wick that transfers heat from the evaporator shell to the wick including escape channels that help to generate the delta P that drives the working fluid about the cooling loop at the same time helping to prevent the switch from nucleate to transition boiling that takes place on flat surfaces and which makes it possible for an LHPL device to cool heat loads with hot spots releasing more than 100 Watts per square cm.

A method for operating a nuclear reactor comprises acquiring a plurality of quantities characterizing the operation of the nuclear reactor; and calculating at least one Departure from Nucleate Boiling Ratio using a deep neural network. The entries of the deep neural network are determined by using the acquired quantities. The deep neural network includes at least two hidden layers of at least five neurons each. The method further includes calculating the deviations between the at least one calculated Departure from Nucleate Boiling Ratio and a plurality of predetermined reference threshold values and formulating a control signal for a reactor control system by using the calculated deviations. The control signal is an automatic reactor shutdown or alarm. The method also includes emergency shutdown of the nuclear reactor or emission of an alarm signal if relevant.

The invention discloses a material corrosion test device and method for simulating a nucleation boiling environment, and belongs to the field of nuclear power. The material corrosion test device for simulating the nucleation boiling environment comprises a circulating system, a test system and a control system, wherein the circulating system provides a circulating pipeline for accommodating a test solution; the test system comprises a test sleeve and a heating module, a test pipe fitting is installed in the test sleeve, and the heating module heats the test pipe fitting in an internal heating mode and provides an axial temperature field distributed in a gradient mode. The control system comprises a void fraction control module, and the output power of the heating module is adjusted according to a void fraction control algorithm so as to accurately control the void fraction formed on the surface of the test pipe fitting. The test device can accurately simulate the corrosion behavior of the fuel rod cladding tube in the nucleation boiling environment under the actual working condition, and has positive significance for improving the prediction precision of the corrosion behavior.

An integrated two-phase immersion cooling system for electronic devices includes a tank containing a dielectric working fluid in which one or more electronic modules are immersed. Each electronic module is thermally coupled to a heat-spreading assembly supporting a boiling-enhancement surface configured to promote controlled nucleate boiling of the dielectric working fluid. Vapor generated at the boiling-enhancement surface rises into a vapor region and is guided toward a condensation assembly, where the vapor is condensed and returned to the working-fluid region through one or more condensate-return pathways. A coolant-delivery subsystem provides directed liquid-phase dielectric working fluid toward the boiling-enhancement surface to reinforce surface wetting, regulate local heat flux, and reduce reliance on bulk fluid circulation. A control subsystem receives thermal and fluidic telemetry, estimates operating states associated with phase-change behavior, and regulates liquid delivery, circulation, and condensation operation to maintain stable two-phase cooling while reducing energy consumption across operating conditions.

The invention relates to the field of nuclear power instrument control, in particular to a reactor core protection system and method, and the system comprises neutron detection equipment which is used for measuring the neutron flux of a reactor core; the upper computer is used for reconstructing reactor core flux power according to the neutron flux so as to generate calibration parameters and sending the calibration parameters to the verification equipment; the verification equipment is used for judging whether the calibration parameters are valid or not according to the neutron flux and the calibration parameters, and sending the calibration parameters to the lower computer when the calibration parameters are valid; the lower computer is used for calculating the minimum deviation nucleation boiling ratio and the local highest linear power density of the reactor core according to the neutron flux and the calibration parameters; and the control equipment is used for controlling a control rod of the reactor core according to the minimum deviation nucleation boiling ratio and the local highest linear power density. According to the invention, the reliability of calibration parameters is effectively improved, and the risk of protection function maloperation is reduced.

The present invention discloses a method and system for optimizing the energy efficiency of a heating furnace, which specifically relates to the field of operation control technology. The method obtains boiling state parameters and structural deformation parameters of a water-jacketed heating furnace during operation, identifies the critical point position of the transition from nucleate boiling to film boiling and the duration of film boiling, and calculates the thermal expansion displacement rate and oscillation phase angle of the furnace shell. The method generates a heat transfer coefficient fluctuation compensation factor by analyzing the phase lag relationship between the boiling phase change cycle and the thermal expansion deformation. The method calculates the heat flux distribution adjustment amount based on the heat transfer coefficient fluctuation compensation factor. The method calculates the dynamic compensation correction coefficient by combining the flow rate change of cooling water and the flow-thermal expansion transfer function. The method controls the power output and cooling water flow of the water-jacketed heating furnace based on the heat flux distribution adjustment amount and the dynamic compensation correction coefficient, thereby realizing dynamic optimization and regulation of the heat transfer behavior of the heating furnace and effectively improving the energy efficiency stability and heat transfer control accuracy of the water-jacketed heating furnace under complex working conditions.

The invention provides a method for predicting and calculating parameters in a precooling process of a horizontal large-pipe-diameter liquid hydrogen pipeline and a related device, and belongs to the technical field of low-temperature precooling. According to the method, in a lower liquid phase, a lower wall surface heat exchange coefficient is obtained according to the size relation between the lower wall surface temperature and the nucleate boiling end point temperature and the film boiling starting point temperature; in the upper gas phase, the upper wall surface heat exchange coefficient is obtained based on the gas phase temperature, the upper wall surface temperature and the gas phase heat conductivity coefficient; establishing a two-dimensional pipeline section temperature distribution calculation equation based on the lower wall surface heat exchange coefficient and the upper wall surface heat exchange coefficient, and discretizing the two-dimensional pipeline section temperature distribution calculation equation to obtain a discretized two-dimensional pipeline section temperature distribution calculation equation; and solving the discretized two-dimensional pipeline section temperature distribution calculation equation in an iterative calculation mode to obtain new upper wall surface temperature and lower wall surface temperature. The problem that the accuracy of parameters obtained in the section precooling process of the horizontal large-diameter pipeline is not high is solved.

The present application relates to a data correction method and device for a nuclear reactor core. The method comprises: obtaining the actual deviation from nucleate boiling ratio (DNBR) of the nuclear reactor core at the acquisition time; obtaining a correction factor for the nuclear reactor core; wherein the correction factor is obtained by processing the theoretical DNBR and self-powered neutron detector (SPND) detection signal of the nuclear reactor core, the first core hot channel position and calibration parameters of the nuclear reactor core in a calibration state, and the failed SPND position and number of failed SPNDs in the presence of a failed SPND; using the correction factor to correct the actual DNBR to obtain the target DNBR of the nuclear reactor core at the acquisition time. The present method can achieve efficient and accurate correction of the actually acquired DNBR in the presence of a failed SPND in the nuclear reactor core.

The application relates to the technical field of electronic heat dissipation, and particularly provides a three-dimensional vapor cavity heat dissipation device, aiming at solving the problems of low natural convection heat dissipation efficiency and poor heat dissipation effect in the prior art. In the application, pseudo-boiling of a working medium in the evaporation cavity is caused, the heat absorption capacity of the working medium is increased, the heat transfer rate of the working medium is improved, heat is transferred to the evaporation fins, the working medium in the evaporation fins is heated to cause nucleate boiling to form a vapor-liquid bubble-shaped mixed flow, the bubbles rise to the condensation fins under the action of buoyancy, partial condensation is completed, the remaining steam is condensed in the condensation cavity and returns to the evaporation fins to be heated and evaporated, and heat dissipation is completed. The application provides the three-dimensional vapor cavity heat dissipation device with high heat transfer, small temperature difference and high heat dissipation efficiency, and can effectively solve the problems of low natural convection heat dissipation efficiency and poor heat dissipation effect.

The present invention relates to an axial oscillating heat pipe grinding wheel reinforced with gradient foam metal at the heat input end and a preparation method thereof, wherein the grinding wheel mainly comprises a base, a cover plate, a tool rod, a working medium, an abrasive layer, and a gradient foam metal. The base is manufactured by optimizing the design by combining a lattice structure and 3D printing technology, and a gradient foam metal is embedded in the oscillating heat pipe flow channel position corresponding to the heat input end. The pore size and porosity of the gradient foam metal gradually increase from the flow channel wall to the flow channel center, and the hydrophilicity gradually decreases, forming a hollow trumpet-shaped structure in which the material thickness gradually increases vertically downward along the axis of the grinding wheel. During the grinding process, the gradient foam metal in the grinding wheel increases the density of the vaporization core in the flow channel due to the porous structure characteristics, accelerates the separation of bubbles in the nucleate boiling process, promotes phase change heat transfer in the tube, and effectively avoids the occurrence of local dry-out phenomenon. The grinding wheel structure can significantly improve the heat conduction capacity and working stability.

This application relates to a method, apparatus, computer equipment, storage medium, and computer program product for analyzing the heat and mass transfer of corrosion products in nuclear reactors. It includes: obtaining the average thermal conductivity of the corrosion products and determining the temperature distribution of the corrosion products in coolant saturation, nucleation boiling, and evaporation states based on the average thermal conductivity; determining the coolant flow rate distribution in the corrosion products based on the pressure distribution; obtaining the concentration relationship between the boric acid concentration and the concentrations of other soluble substances in the coolant, and determining the concentration distribution of other soluble substances based on the concentration relationship and the boric acid concentration; analyzing the internal heat and mass transfer of the corrosion products based on the temperature distribution, flow rate distribution, and concentration distribution of soluble substances to obtain the concentration of boron enriched within the corrosion products, and obtaining the total boron deposition based on the enriched concentration. This method can accurately analyze the heat and mass transfer of corrosion products in nuclear reactors.

The invention relates to the field of heat dissipation devices, and provides a phase change heat dissipation device. The phase change heat dissipation device comprises a sealed cavity, and the sealed cavity is provided with a heat transfer face used for making contact with a heat source, a working medium inlet and a working medium outlet. The macroscopic turbulent flow structure is arranged in the sealing cavity and is used for generating a transverse velocity component and a secondary flow in a working medium flowing through the sealing cavity so as to damage and reconstruct a near-wall boundary layer; and the microscopic nucleation structure is arranged on the heat transfer surface or the surface of the macroscopic turbulent flow structure and is used for providing bubble nucleation points. The phase change heat dissipation device can accelerate heat transfer, start nucleate boiling in advance, effectively meet the requirement for high-heat-flux heat dissipation and solve the problem that a traditional device is low in heat exchange efficiency. The limitation that a traditional phase change heat dissipation device is prone to failure under the high heat flux density is broken through, and the application range is expanded.

Provided is a cooler and a cooling device capable of inducing boiling at a low degree of superheat by suppressing an increase in the Onset of Nucleate Boiling. A cooler of a boiling method type for cooling a heat generating body, comprising: a container for storing a working fluid; a cooling member made of a porous body and disposed in the container so as to face a surface of the heat generating body; and at least one thin metal wire or thin metal film disposed between the surface of the heat generating body and the cooling member and configured to be heatable.

The invention discloses a spraying enhanced two-phase evaporation type flat plate loop heat pipe evaporator and a heat dissipation system, and relates to the technical field of heat management of high-heat-flux electronic devices. The evaporator comprises an evaporator base plate, wherein a liquid gathering groove and a steam groove network are arranged on the evaporator base plate; a double-layer capillary core consisting of a fine-hole capillary core and a coarse-hole distribution layer, a liquid baffle with uniformly distributed through holes and an upper cover plate are sequentially covered above the liquid gathering groove and are jointly closed to form a steam cavity, an active spraying device is arranged, condensate is actively sprayed to the area of the liquid gathering groove, and a stable liquid film is formed through the distribution of the double-layer capillary core; steam generated by boiling is guided to a single-end steam confluence area through a steam groove network in a low-resistance mode, and gas-liquid isolation is achieved through a liquid baffle to prevent high-speed steam entrainment. According to the invention, the evaporation area stably maintains the rich liquid nucleate boiling state, the capillary core drying is effectively inhibited, the stable heat dissipation of the extremely high heat flux of over 300W / cm is realized, and the method is suitable for the heat management of high-power chips such as a GPU (Graphic Processing Unit), an AI (Artificial Intelligence) accelerator and the like.

The present application relates to the field of special glass processing, and discloses a heat-resistant and heat-insulating tempered coated glass and a preparation process thereof, which comprises the following steps: radiating a glass substrate to a preset temperature; spraying a gas-liquid multiphase medium containing a gas-phase precursor and a liquid coolant; using a velocity slip field in a jet field to drive the precursor to contact the glass surface first, and in-situ inducing thermal decomposition to generate nanocrystal nuclei; penetrating the vapor film generated by the liquid coolant through the crystal nuclei to trigger the heat exchange mode to cross from film boiling to nucleate boiling, and forming a compressive stress layer; using thermophoretic force to drive the deposition components to diffuse to the glass surface layer to build a component gradient layer, the present application breaks through the interface thermal resistance bottleneck through an in-situ nucleation mechanism, improves the quenching heat exchange intensity, solves the stress relaxation and film layer peeling problems caused by the step-by-step process, realizes the chemical bonding of the film layer and the substrate, and synergistically enhances the mechanical strength and heat shielding performance of the glass.

The utility model discloses an evaporating pipe, which relates to the technical field of heat exchange equipment and comprises a pipe body and a plurality of bosses, a plurality of inner spiral fins are wound on the inner surface of the pipe body, and a plurality of outer spiral fins are wound on the outer surface of the pipe body to form a spiral medium channel; the multiple bosses are distributed on the outer surface of the outer spiral fin, the cross section of each boss is in a leaf shape, the cross section of each boss is gradually reduced from outside to inside, a gap is formed between every two adjacent bosses, the width of each area of each gap is smaller than that of the corresponding medium channel, and a cavity structure is formed between each medium channel and the corresponding boss. The cavity structure is provided with a large heat exchange surface, under the heat exchange working condition, the liquid working medium is rapidly boiled and disengaged from the heat exchange surface, the heat exchange working condition can be kept to be nucleate boiling instead of film boiling, the evaporation pipe has high evaporation heat exchange performance and efficiency, and then the heat exchange efficiency of the shell-and-tube heat exchanger is improved.

To provide a method for determining a cooling condition of a material to be cooled capable of separately adjusting cooling of a film boiling region and cooling of a nucleate boiling region while coping with a rapid change of a heat transfer coefficient in a transition boiling region, and improving flexibility.SOLUTION: A n (T) represents a heat-transfer coefficient α (W / (m2K)) when the surface temperature T (°C) of the cooled material is in a nucleate boiling region; The heat-transfer coefficient α is expressed by an equation including (1-Pc)·α n (T) + Pc·α f (T), where α f (T) represents the heat-transfer coefficient α when the surface temperature T is in the film boiling region, and Pc represents the heat-transfer coefficient α that approaches 0 as the surface temperature T decreases and approaches 1 as the surface temperature T increases at least when the surface temperature T is in the transition boiling region.SELECTED DRAWING: Figure 1

The application provides a method and product for determining a mixed core deviation from nucleate boiling ratio design limit value, and the method comprises the following steps: obtaining a first deviation from nucleate boiling ratio design limit value of a full core of a mixed core; determining a target fuel assembly in at least two fuel assemblies of the mixed core, and the deviation from nucleate boiling ratio of the target fuel assembly represents the minimum deviation from nucleate boiling ratio of the mixed core; and determining the deviation from nucleate boiling ratio design limit value of the mixed core according to the relationship between the deviation from nucleate boiling ratio of the target fuel assembly and the first deviation from nucleate boiling ratio design limit value. The application determines the target fuel assembly whose deviation from nucleate boiling ratio represents the minimum deviation from nucleate boiling ratio of the mixed core, and determines the deviation from nucleate boiling ratio design limit value of the mixed core based on the relationship between the deviation from nucleate boiling ratio of the target fuel assembly and the first deviation from nucleate boiling ratio design limit value, so that the efficiency and accuracy of determining the deviation from nucleate boiling ratio design limit value of the mixed core can be improved.

A thermal management system that uses flow regime identification information obtained from a flow sensor to control heat exchanger operation so it is maintained at or below the Critical Heat Flux point. The flow sensor is integrated with a controller to control the liquid flow rate and temperature inside and / or outside the heat exchanger such that the heat flux stays below the Critical Heal Flux point while at the same time being in the nucleate boiling flow regime.

This invention discloses a two-phase immersion liquid-cooled finned grooved chip heat dissipation control system based on thermal management, relating to the field of chip heat dissipation technology. It includes: a data-driven sensing module for real-time acquisition of heat dissipation status monitoring data, data preprocessing, and determination of bubble retention degree, implementing graded vibration and cooling regulation; a heat flux diagnosis and control generation module for constructing a coupled heat flux acoustic digital twin model, assessing the intensity of thermal risk control, and determining the vibration regulation level; a vibration regulation execution module for implementing vibration debubbling at different vibration regulation levels for active heat dissipation control; and a feedback and parameter optimization module for evaluating the vibration regulation effect based on heat dissipation status monitoring data before and after vibration regulation, and performing vibration regulation feedback and optimization. This solves the problem that under high heat flux density conditions, the accumulation of small bubbles on the chip surface makes it difficult to maintain an efficient and stable nucleate boiling state, thus affecting the chip's cooling effect and operational safety.

The application provides a nucleate boiling device and a processing method of the nucleate boiling device. A wall surface of a cavity of the boiling device is provided with a bubble cavity, and roughness of the wall surface is less than or equal to Ra0.05. In this way, by reducing the roughness of the wall surface and by the arrangement of the bubble cavity, the wall surface is smooth enough, so that the generation of bubbles is avoided in places other than the bubble cavity, and the growth position of the bubbles is guided to the bubble cavity for growth, so that the position of the bubbles is determined, and the accuracy of observation and analysis of the bubbles is improved.

The present application discloses an online protection method, device, medium and equipment for a reactor core. The method includes: obtaining the rod position information of each control rod in the reactor under the current state, and obtaining the full-core power reconstruction coefficient under the current state according to the rod position information and a preset rod state database; calculating the linear power density and departure from nucleate boiling ratio of each fuel assembly channel, and the linear power density and departure from nucleate boiling ratio of the entire reactor based on the full-core power reconstruction coefficient, detector current signal and plant operating condition signal under the current state; comparing the linear power density of each fuel assembly channel, the linear power density of the entire reactor with a preset linear power density threshold, and the departure from nucleate boiling ratio of each channel, the departure from nucleate boiling ratio of the entire reactor with a preset boiling ratio threshold, and determining and outputting a pre-protection signal and protection information. By involving the reactor power reconstruction coefficient in the calculation of protection parameters, the accuracy and reliability of the protection signal are improved, and the safety of the power plant is enhanced.

A nucleate boiling apparatus is disclosed that includes a base configured to fit onto a heat-producing object to provide immersion cooling to the object in a liquid-cooled computing environment. The apparatus further includes first and second pluralities of pipes extending from opposite sides of the base. Each of the first and second pluralities of pipes including a respective transition region and a respective flat region. The first and second pluralities of pipes in the transition regions extend away and up from the base, and the first and second pluralities of pipes in the flat regions extend away from the base in a fanned-out arrangement. The flat region of the second plurality of pipes is at a greater distance from the base than the flat region of the first plurality of pipes.

The present invention discloses a composite microstructure surface with sidewall-coupled microtubes for enhancing boiling performance. The surface is based on a regularly arranged microcolumn array, and a number of microcolumn units are arranged on a microcolumn substrate. By symmetrically opening microtubes extending to the top surface of the microcolumns on the microcolumns, the orderly coupling of the microcolumns and microtubes is achieved, and a three-level liquid replenishment system is constructed, which is liquid supply channel-groove-microtube from macro to micro, thereby enhancing the liquid replenishment capacity of the microstructure surface, improving the critical heat flux density of the surface, and delaying the occurrence of boiling crisis; the microcolumn units distributed in the array can effectively adjust the growth size of the bubbles, and the liquid supply channels between the arrays can effectively alleviate the lateral merging between the bubbles, delay the occurrence of film boiling, and maintain the stability of efficient nucleate boiling heat exchange. In addition, the composite microstructure surface proposed by the present invention is processed and formed in one step by deep silicon etching, and the processing technology is simple, which can realize large-scale commercial production and has high economic benefits.