224 results about "Counting rate" patented technology

The invention discloses a high-speed multi-photon detection system and method. The system comprises a detector and a signal processing circuit, wherein the detector is composed of a window plated with a photoelectric cathode, a micro-channel plate stack and an anode; a plurality of incident photons are converted into a plurality of photoelectrons by the photoelectric cathode, and the photoelectrons are converted into electron cloud by the micro-channel plate stack; the incident electron cloud is divided into multiple paths by three layers of staggered metal strip electrodes of the anode, and charge collection is carried out to obtain charge short pulses of each layer of electrode; the signal processing circuit converts the charge short pulses transmitted by the three layers of electrodes into digital pulse signals, obtains the centroid coordinates of the electron cloud from the digital pulse signals as the abscissa value, the ordinate value and the verification value of the incident photon position, combines the abscissa value, the ordinate value and the verification value based on the screening condition to obtain the target two-dimensional coordinates, and finally obtains the target two-dimensional coordinates. And transmitting to a terminal for imaging display. According to the invention, a plurality of synchronous photons can be detected, the overall counting rate of the detector is greatly improved, and the detection efficiency is improved.

The embodiment of the invention relates to the technical field of nuclear detection and measurement, and discloses a double-label nuclide analysis method and device and a program product, and the method comprises the steps: measuring a standard quenching source, and obtaining an external standard source spectrum index of the standard quenching source; drawing a correction curve by taking the external standard source spectrum index as an independent variable; measuring the double-labeled sample under external gamma source high voltage, and obtaining and calculating an external standard source spectrum index of the double-labeled sample through external gamma source spectrum stripping; determining the counting efficiency of low-energy nuclide, the counting efficiency of high-energy nuclide, the spectrum index of the low-energy nuclide sample and the spectrum index value of the high-energy nuclide sample corresponding to the double-labeled sample under the current quenching level according to the external standard source spectrum index of the double-labeled sample and the correction curve; the method comprises the following steps: measuring a double-labeled sample under double-labeled high pressure to obtain a full-spectrum counting rate and a full-spectrum sample spectrum index of the double-labeled sample; the low-energy nuclide activity and the high-energy nuclide activity of the double-labeled sample are calculated based on the parameters, so that the operability is higher, the accuracy is higher, and the application range is wider.

Disclosed are a neutron dose measurement apparatus and a neutron capturing treatment device. The neutron dose measurement apparatus includes a measurement unit for receiving neutrons and outputting signals, a signal processing unit for processing the signals output from the measurement unit, a counter for counting the signals output from the signal processing unit to obtain a count rate, and a count rate correction unit for correcting the count rate.

The invention relates to the field of crystal detection, and discloses a multifunctional comprehensive scintillation crystal and semiconductor material energy spectrum test system, which comprises a crystal adaptation module for judging the type and size of a placed crystal through an optical identification and parameter matching mechanism, and a signal acquisition module for amplifying, filtering and digitally processing an acquired signal, the signal correction module is used for correcting waveform distortion and baseline drift through a dynamic gain adjustment algorithm of a low-noise pre-amplifier and a multi-channel pulse analyzer; the data analysis module is used for generating an energy spectrum curve according to input signals and calculating energy resolution, counting rate, light attenuation time or carrier mobility, and the environment calibration module is used for dynamically evaluating shading degree, environment light, temperature and electromagnetic interference through an optical sensor and a temperature and humidity detector in the camera obscura and outputting updated calibration parameters. The method has the advantages of improving the detection efficiency, precision and consistency.

The invention relates to the field of LED display screen defect detection, in particular to an LED display screen defect rapid detection method. The method specifically comprises the steps that polarization entangled photon pairs are generated through a first detection assembly, the photon pair coincidence counting rate is measured through an HOM interferometer and a single-photon detector in a second detection assembly, and a photon pair anomaly distribution diagram is generated; establishing a correlation model of the photon pair coincidence counting rate and the electronic state density, and analyzing internal defects of the display screen; an integrated high-speed CMOS camera and a multiband LED annular light source are adopted to collect four-channel image data, and features are extracted to generate an image data abnormal probability graph; and finally, integrating a quantum optical measurement result and an image analysis result through coordinate mapping, judging a final defect area and type based on a decision tree rule, and covering various defect types such as material internal defects, surface reflection abnormity and color unevenness. According to the method, the efficiency and the accuracy of LED display screen defect detection are remarkably improved.

The invention relates to the technical field of single-photon detection, in particular to a single-photon detector performance parameter measurement method, device and equipment and a storage medium, and the method comprises the steps: building a statistical histogram of time domain interval data, and building the statistical distribution characteristics of the photon counting rate and dark counting of a single-photon detector; the probability of no photon detection event in the duration of the optical pulse and the ideal probability of no dark pulse in a preset time window are defined based on the statistical distribution characteristics, and then the probability of generating a single photon signal by the periodic optical pulse is calculated based on the obtained parameters; and finally, determining a periodic statistical peak count value based on the statistical histogram and the probability of generating the single photon signal by the periodic light pulse, and calculating an average detection photon number and a dark count rate so as to obtain the dead zone time, so that information such as the average detection photon number, the dark count rate and the dead zone time of the single photon detector is simultaneously represented through one-time data acquisition, and the detection accuracy of the single photon detector is improved. The problems that in a traditional method, the data storage amount is large, and cost is high are solved.

The invention provides a dynamic PSD threshold value correction method, device and equipment suitable for digital pulse waveform discrimination, and relates to the technical field of nuclear radiation detection.The method comprises the steps that a current PSD-energy two-dimensional spectrum is obtained through a nuclear radiation detecting instrument, counts in a target energy range in the current PSD-energy two-dimensional spectrum are removed, and the current PSD-energy two-dimensional spectrum is obtained; converting into a one-dimensional PSD spectrum by using a preset formula; determining the position of the maximum peak and the full width at half maximum in the one-dimensional PSD spectrum, determining a PSD threshold value, and resetting the target PSD value range according to the PSD threshold value; and obtaining the target PSD-energy two-dimensional spectrum again, carrying out statistics on the discrimination target ray counting value and the total counting value, and determining a main target ray counting value according to a difference value between the total counting value and the discrimination target ray counting value so as to determine a main target ray counting rate and a discrimination target ray counting rate. By regularly and automatically analyzing the PSD-energy two-dimensional spectrum and dynamically adjusting the PSD threshold value, different particles can be more accurately discriminated, and the particle detection accuracy and efficiency are improved.

The invention discloses a two-photon N00N quantum state intelligent regulation and control device and method, and the device comprises an intelligent regulation and control module, and an entangled photon pair generation module, an HOM interferometer and a data collection module which are connected in sequence, and the entangled photon pair generation module transmits polarized orthogonal entangled photon pairs to two light paths in the HOM interferometer respectively; the data acquisition module is used for detecting and counting photons output by the two light paths respectively; the intelligent regulation and control module controls the first electric control time delay line on one light path and the electric control polarization controller on the corresponding light path so as to regulate the light path difference of the two light paths and the polarization state of photons output by the corresponding light path; every time control is completed, a second electric control time delay line on the other light path is controlled to carry out time delay scanning according to a set rule, and a coincidence counting rate and HOM visibility are obtained; and according to the coincidence counting rate and the HOM visibility, determining whether the two-photon N00N quantum state generated under the control is good or bad. According to the invention, intelligent regulation and control of the two-photon N00N quantum state quality can be realized.

The invention relates to the technical field of data calibration, in particular to a neutron fluence response calibration method based on a neutron generator reference radiation field, and the method comprises the steps: collecting a counting rate and a neutron fluence rate at each moment in each monitoring period through a neutron detector and a neutron generator; data of each environmental parameter around the reference radiation field at each moment in each monitoring period are obtained; recording each monitoring period and a plurality of monitoring periods before the monitoring period as historical periods; determining the measurement error of each historical period; obtaining the measurement interference degree of each environmental parameter in each monitoring period; and calculating the scattering interference degree of each environmental parameter in each monitoring period to obtain a calibration counting rate, and carrying out real-time calibration on the neutron fluence response. According to the invention, the interference influence of different environmental factors on the measurement result of the neutron detector can be quantified through dynamic environmental changes, the measurement result of the neutron detector is calibrated in real time, and the measurement accuracy of neutron fluence response is improved.

The invention relates to a Lu-177 activity direct measurement method, a Lu-177 activity direct measurement device and a processor. The method comprises the following steps: constructing a first calculation model for calculating the detection efficiency of a Lu-177 sample; the Lu-177 sample and the blank sample corresponding to the Lu-177 sample are measured, and the counting rate of the Lu-177 sample under different coincidence conditions is obtained; calculating detection efficiency based on the counting rate and a first calculation model; and calculating the activity of the Lu-177 sample based on the detection efficiency, the counting rate and an activity calculation model. Compared with the prior art that the low uncertainty level can be achieved only by carrying out dilution measurement in a laboratory or the high uncertainty level of field direct measurement is achieved, the method has the advantage that the accurate activity of the Lu-177 sample can be obtained by carrying out direct measurement and calculation in the laboratory or the field on the premise that dilution is not carried out. The method meets the requirements of simple and convenient sample preparation, recoverable nuclide and low uncertainty.

The invention relates to a signal acquisition device of a cadmium zinc telluride detector based on multiple channels, which is characterized in that a multi-channel parallel processing unit, a dynamic baseline drift correction unit, a self-adaptive dead time control unit and an energy spectrum reconstruction and trailing suppression unit are mutually matched; reverse compensation current can be injected into each channel through the dynamic baseline drift correction unit so as to adjust the output of each channel, and low-frequency noise interference is eliminated in combination with a digital filtering algorithm. The dead time can be dynamically adjusted according to the current channel counting rate through the self-adaptive dead time control unit, multiple counters are started to work alternately in a first counting rate mode, and counter resources are combined in a second counting rate mode to improve the resolution; through the energy spectrum reconstruction and trailing suppression unit, a charge collection curve can be fitted through correlation analysis of timestamps and amplitude data, hole trailing signals are recognized, counter shielding logic is triggered, related noise interference is reduced on the whole, and signal collection accuracy is improved.

A method of determining downhole formation oil saturation and three-phase holdup is described. The method includes lowering a pulsed-neutron logging tool downhole with a near detector and a far detector. The method further includes measuring a carbon to oxygen ratio from the near detector, measuring a carbon to oxygen ratio from the far detector, measuring a ratio of inelastic count rates, and plotting the measured ratios in a prismatic grid. The method further includes visualizing the fluid volumetrics around the pulsed-neutron logging tool.

The invention discloses a single-photon detector post-pulse probability suppression method and system, and the method achieves the measurement of the arrival time of a detection pulse after a previous detection pulse, abandons the detection pulses in a certain time range, reduces the post-pulse probability, does not need to close a gate signal and hardware processing, and does not affect the performance of a detector. The post-pulse probability time distribution characteristics of the single-photon detector can be identified by means of a time periodic folding measurement scheme, so that the optimal suppression time window of the post-pulse probability of the single-photon detector can be reasonably adjusted according to the relationship between post-pulse probability distribution and the saturation counting rate, and the optimal detector performance is realized. The method has the characteristic of universality, is not only applied to a sine gating detector, but also can be applied to scenes such as a rectangular gating detector and a free operation detector which need to further suppress the post-pulse, and does not affect the original detection process.

The invention discloses a muon detector with variable scintillator spacing, which comprises a supporting base, and a bottom plate is arranged at the upper end part of the supporting base; the lower-layer detection part is fixedly arranged at the end part of the bottom plate, a multi-stage mechanical telescopic mechanism is arranged on the bottom plate, and an upper-layer detection part is arranged at the end part of the multi-stage mechanical telescopic mechanism; the main control data acquisition system is electrically connected with the multi-stage mechanical telescopic mechanism, the upper-layer detection part and the lower-layer detection part, and is used for setting and acquiring a distance value between the upper-layer detection part and the lower-layer detection part; and calculating according to the collected real-time spacing value, and performing corresponding data correction and image reconstruction according to the effective detection range and the optimal detection area under the current configuration. According to the method, the spatial resolution and the counting rate can be dynamically adjusted, so that the performance limitation caused by a fixed spacing design is broken through, and the comprehensive efficiency in a complex detection task is remarkably improved.

The invention provides a flow cytometer light path calibration method, which belongs to the technical field of flow cytometers, and comprises the following steps: firstly, collecting light path detection original data of standard fluorescent microspheres, including laser spot position coordinates, detector output voltage value, dark counting rate and signal counting rate; then establishing a detection channel conversion cost matrix, and calculating an optimal light path detection sequence by using a traveling salesman problem optimization algorithm; adjusting the positions of a laser, an optical filter and a detector according to the optimal sequence, and obtaining optical path calibration data; the collected parameters are substituted into an optical path parameter optimization equation set to be solved, and an optical path collimation coefficient, a detector response coefficient, a signal crosstalk coefficient and an optimal gain value are obtained; and finally, respectively adjusting the position of the laser, the working voltage of the detector, the position of the optical filter and the voltage of the photomultiplier according to the coefficients to finish the accurate calibration of the optical path. The problems that an existing method depending on artificial experience is low in efficiency and overall optimization of a system level is difficult to achieve are solved.

The invention discloses a dynamic threshold adjusting system based on a silicon photomultiplier receiver and a laser radar, and belongs to the technical field of photoelectric detection. According to the system, an incident light signal is captured in real time through a silicon photomultiplier receiver, a pulse counting rate is extracted by a signal processing module to represent ambient light intensity, and an SiPM detection threshold value is adjusted based on a dynamic feedback mechanism: when background light is enhanced, the threshold value is increased to suppress noise pulses; when the background light is weakened, the threshold is reduced to preserve the weak signal. A grey-scale map generation module is introduced, noise distribution of multi-channel SiPM is converted into a two-dimensional grey-scale map through a space mapping algorithm, and accurate positioning of a noise source and collaborative optimization of a regional threshold are achieved.

A nanoscale temperature detector comprising a diamond sensing probe (1) having a lateral dimension of at least 200 nanometers and having a sensing tip (2) with a radius of curvature (R) of less than 100 nanometers, less than 10 nanometers or less than 1 nanometer and a plurality of color centers (5) showing temperature sensitive features in the emission count rate. The diamond sensing probe (1) has a lateral dimension of at least 200 nanometers and is connected to a detector system (13) by a mounting structure (6). A thermal isolation barrier (3) thermally separates the sensing probe (1) from the detector system (13).

The invention discloses a medical image coincidence event processing method, system and device, equipment and a medium. The coincidence event processing method for the medical image comprises the steps that an original event is obtained, and the original event is an event composed of single photons and obtained by collecting photons generated by decay of a radioactive tracer through a detector; based on the energy information and the time information of the original events, the original events are discriminated, effective events are obtained, the effective events comprise true coincidence events and random coincidence events, and the true coincidence events are used for medical image reconstruction; determining a time window for the detector to collect photons, and dynamically adjusting the window width of the time window based on the change trend of the event counting rate; the valid events are processed based on the time window to reduce random coincidence events in the valid events.

The application discloses a kind of arbitrary waveform nuclear pulse conversion methods, for the trapezoidal shaping of arbitrary waveform nuclear pulse signal.First, the arbitrary waveform nuclear pulse signal is regarded as the impulse response of rational fraction transfer function system.Second, rational fraction transfer function is decomposed into multiple first-order inertia link and the form of sum, then, multiple first-order inertia link and the form of sum is carried out Laplace inverse transformation into time domain expression, and then its time domain expression is discretized and transformed, then the parameter of discretized expression is obtained using particle swarm algorithm, finally, the transfer function of trapezoidal shaping and shaping recurrence formula are obtained, the trapezoidal shaping of arbitrary waveform nuclear pulse signal is realized to a certain extent, the symmetry of trapezoidal pulse is improved, the accurate acquisition of pulse amplitude is facilitated, the energy resolution of system is improved and the counting rate is improved, which has great significance for improving the precision of radioactivity measurement.

The invention provides an online diagnosis and repair method for a uranium mine gamma ray monitoring device, and the method comprises the steps: determining the respective counting rate correction values of a plurality of detectors based on the current working temperature of the uranium mine gamma ray monitoring device, a preset temperature compensation model, and the counting rate detection values of the plurality of detectors; based on the respective counting rate correction values of the plurality of detectors, the detection efficiency of each detector is determined, and the detection efficiency comprises static detection efficiency and dynamic detection efficiency; and if the detection efficiency of any first detector in the plurality of detectors is deviated from the detection efficiency of a specified second detector in the plurality of detectors, circuit parameters of the first detector are adjusted based on the deviation, so that the detection efficiency of the first detector after the circuit parameters are adjusted is consistent with the detection efficiency of the second detector. According to the technical scheme, the measurement precision and the detection efficiency of the uranium ore gamma ray monitoring device in continuous operation are improved, and the uranium ore sorting energy efficiency is improved.

The present invention provides a method for three-dimensional positioning of radioactive materials indoors, comprising: step S1, establishing a UWB positioning system; step S2, establishing a Cartesian coordinate system for the indoor environment; step S3, obtaining positioning information of a nuclear detector and the count rate at that location; step S4, collecting the count rates of two adjacent fixed-angle detectors A and B at the same horizontal location; step S5, collecting the count rates of two adjacent fixed-angle detectors A and C at the same vertical location; step S6, inverting to obtain α; step S7, inverting to obtain α1; step S9, measuring the distance between the detector and the radioactive material; and step S10, calculating the coordinates of the radioactive material. The present invention also provides a three-dimensional positioning system for radioactive materials indoors.

The invention discloses an anti-interference measurement system of an out-of-pile pulse type detector, which comprises an FPGA (Field Programmable Gate Array), and the FPGA is characterized in that in a normal working state, a test module controls a channel selection module to be switched to a measurement channel; the signal processing module performs validity detection on the signal waveform, generates a fault information data packet and sends the fault information data packet to the fault management module if the signal waveform fails, performs three-path parallel processing on the signal if the signal waveform is valid to obtain the signal waveform, timestamp information and a signal type, and obtains counting rate information of the signal according to the signal type and the timestamp information; an interference signal data packet and a nuclear signal data packet are generated and sent to the communication module, the signal processing module detects the validity of signal waveforms and timestamps in real time, and when the signal waveforms and the timestamps fail, a fault information data packet is generated and sent to the fault management module; the parameter module carries out self-recovery processing, and the test module and the signal processing module verify the self-recovery effect. The system improves the anti-interference capability, accuracy and reliability of measurement.

The invention discloses a measuring method and device for the radial detection depth of a near-bit azimuth gamma tool while drilling. The measuring method comprises the steps that an azimuth gamma receiving short section is arranged around an azimuth gamma transmitting short section; according to the outer diameter of the azimuth gamma emission nipple, a gamma source rock core with the radiation intensity matched with the inner diameter is selected; the gamma source core is arranged outside the azimuth gamma emission short section in a sleeving mode; testing the gamma counting rate of the near-bit azimuth gamma while-drilling tool; increasing the radial width of the gamma source rock core, and testing the gamma counting rate; when the gamma source core is increased from a target radial width and the gamma counting rate cannot be increased, the target radial width is the radial detection depth of the near-bit azimuth gamma while-drilling tool under a radiation intensity; the gamma source cores with different radiation intensities are replaced, and radial detection depths under different radiation intensities are measured. According to the method, the intuition and the reliability of a measurement result are improved, so that field geosteering and well track adjustment can be guided and supported more accurately.

The invention relates to a method for radiation detection chip angle response compensation. The method comprises the following steps: step 1, testing the counting rate of deposition of each channel of array SiPM when gamma rays have different incident angles; 2, according to a standard dose rate value and the counting rate of each channel of the array type SiPM at different incident angles obtained in the step 1, constructing a linear equation set; 3, solving the system of linear equations in the step 2 to obtain an angle response correction matrix; and 4, correcting the angle response of the chip according to the angle response correction matrix in the step 3. According to the invention, the angle response compensation of the thin-layer scintillator radiation detection chip on the directional dose rate of different incident angles is realized, and the problem of measurement deviation of the radiation detection chip caused by the change of the incident angle of the radiation source is solved.

The invention provides a runner chamber wall thickness and void synchronous detection method, and relates to the technical field of hydro-power engineering nondestructive testing, S1, modular calibration: preparing a combined simulation block of a metal standard plate and an organic material plate, establishing a concrete water content inversion model and a void depth model segmented according to the thickness of a steel lining, and outputting calibration parameters; s2, field data acquisition: arranging measuring lines along a vertical welding seam and a longitudinal rib plate of the runner chamber, acquiring ultrasonic echo time and a thermal neutron counting rate, correcting the wall thickness in combination with the temperature of a steel lining, performing secondary verification on an abnormal measuring point, and outputting an original data set S = {}; and S3, machine learning signal processing: performing wavelet packet decomposition to extract energy ratio characteristics, and calculating thermal neutron counting rate fluctuation characteristics. Precise collaborative detection of the wall thickness and the void is realized through a link-by-link process of modular calibration, field data acquisition, machine learning signal processing, segmented collaborative modeling and Internet of Things data management.

To provide a radioactive material monitoring device capable of accurately detecting the concentration of radioactive materials in a liquid to be detected. [Solution] A radioactive material monitoring device comprising a flow channel through which a liquid to be detected flows, a counter unit that counts signals based on radiation generated from within the flow channel, and an analysis unit that calculates the concentration of radioactive material in the liquid to be detected based on the radiation count rate obtained from the counter unit, wherein the analysis unit includes a background correction unit that calculates a background value from the count rate based on the volume of the liquid to be detected in the flow channel and the count rate obtained from the counter unit, and a concentration calculation unit that calculates the concentration of radioactive material in the liquid to be detected based on the background value calculated by the background correction unit and the count rate obtained from the counter unit.

The invention relates to a method and a system for determining working parameters of a nuclear reactor fission chamber detector. The method comprises the following steps: acquiring output current relation information of a detected detector; determining a working voltage test range of the detected detector according to the output current relation information; and sequentially setting the working gas pressure of the detected detector as a plurality of preset gas pressure values, and controlling the detected detector to work based on the working voltage test range after setting the working gas pressure each time. Obtaining and determining counting rate data corresponding to each predetermined air pressure value according to the output current when the neutron beam is injected into the detected detector; and determining ideal working parameters of the detected detector according to the counting rate data. The method can help a worker determine ideal working parameters of the fission chamber detector, and improves the working stability and reliability of the detector.

The invention relates to the field of laser welding quality detection, in particular to a multi-modal fusion identification method and system for laser welding defects of copper-aluminum heterogeneous materials. Molten pool images, temperature fields and acoustic emission signals are synchronously collected through a visible light high-speed camera, a thermal infrared imager and an acoustic emission sensor which are coaxially integrated; the width oscillation amplitude, the trailing edge solidification angle, the interface temperature gradient, the acoustic emission characteristic frequency band energy ratio and the burst signal counting rate of the molten pool are extracted; constructing a fusion vector input adaptive weighted deep neural network model, and identifying four types of defects of pores, cracks, incomplete fusion and interface brittle compound layer standard exceeding in real time; and the identification result triggers laser power modulation or protective gas proportion adjustment. The problems that in the prior art, multi-physical field perception is insufficient, the feature adaptability of heterogeneous materials is poor, and real-time control is lack are solved, the defect detection rate reaches 98.2%, and control response delay lt is achieved; and 50ms.

According to the method for regulating and controlling the current density of the superconducting micron wire, the hole shape with a certain size is designed in the linear area of the winding superconducting micron wire, so that the current density of the superconducting micron wire is redistributed, the current density at the corner of the winding superconducting micron wire is reduced, and the current crowding effect of the superconducting micron wire is effectively relieved. According to the current density regulation and control method, the superconducting micron wire is allowed to work under higher overall bias current without causing too high dark counting, so that the photon counting rate upper limit of the detector is improved. According to the invention, the detection efficiency of the superconducting micron wire can be improved, dark counting and time jitter are reduced, the structure is simple, the current density is flexible to regulate and control, meanwhile, the device is easy to expand to the development of a large photosensitive area detector, and the device has a wide application prospect in the fields of quantum communication, bioluminescence imaging, dark substance detection and the like.

This invention relates to the fields of nuclear detection electronics and radiation signal processing technology, specifically to an intelligent analysis system and method for nuclear radiation data. The system includes: acquiring a discrete voltage sequence output by the detector; marking pulse signals as clean pulses and calculating the real-time decay constant; calculating the net signal amplitude using a digital twin state-space recursive model; determining the real-time count rate based on the net signal amplitude and calculating the dynamic time window width based on the real-time count rate; discretely accumulating the net signal amplitude based on the dynamic time window width to generate a single-particle physical energy value; determining the measured peak position based on the single-particle physical energy value and generating a gain adjustment coefficient by combining the measured peak position with the real-time decay constant; and outputting a gain control signal based on the gain adjustment coefficient. This invention ensures precise synchronization between the subsequent calculation model and the current physical state of the detector, thereby significantly improving the physical authenticity and accuracy of energy spectrum analysis under varying temperature conditions.