101 results about "Fluence rate" patented technology

The invention relates to techniques for measuring and comparing relative molecular flux rates of different biological molecules by administering isotope-labeled water to one or more tissues or individuals and comparing the molecular flux rates of two or more biological molecules, including biological molecules in different chemical classes. The methods find use in several applications including diagnosing, prognosing, or monitoring a disease, disorder, or condition, the in vivo high-throughput screening of chemical entities and biological factors for therapeutic effects in various disease models, and the in vivo high-throughput screening of chemical entities and biological factors for toxic effects.

Disclosed here is a method for measuring the kinetics (i.e., the molecular flux rates—synthesis and breakdown or removal rates) of a plurality of proteins or organic metabolites inn living systems. The methods may be accomplished in a high-throughput, large-scale automated manner, by using existing mass spectrometric profiling techniques and art well known in the fields of static proteomics and static organeomics, without the need for additional biochemical preparative steps or analytic/instrumental devices.

Treatment of neoplastic or non-neoplastic dermatological conditions is achieved by administration and photodynamic activation of photosensitizers and pro-photosensitizers by coherent and/or incoherent light. The treatment does not cause clinically signification side effects such as purpura of the treated skin.

A method of treating a subcutaneous fat region is provided. The method includes generating electromagnetic radiation having a wavelength of about 1,200 nm to about 1,230 nm and delivering an average power density of less than or equal to about 2.3 W/cm² of the electromagnetic radiation to the subcutaneous fat region for at least 300 seconds. The method also includes cooling an epidermal region and at least a portion of a dermal region overlying the subcutaneous fat region for at least a portion of the at least 300 seconds. The method further includes causing necrosis of at least one fat cell in the subcutaneous fat region.

The invention discloses an experimental method for single event effects (SEE) of a pulse width modulator (PWM) and belongs to the technical field of space radiation effects and hardening. The method comprises the following steps of: numbering test samples; inserting the numbered test samples into a board, wherein a tested circuit board moves in accordance with a movable bracket; performing a power-on test on a test system; starting a radiation source; in a radiating process, monitoring the single event effects of the tested samples in real time by using a monitoring system; monitoring the fluence rate of incident particles in real time by using a beam monitoring system; and recording the number of the single event effects, the electrical parameters of the samples and the radiation time. The method can realize an evaluation test on the anti-SEE performance of a PWM device and obtain a single particle LET threshold or an energy threshold or a sigma-LET or E curve of the PWM device.

A method for conducting a device proton signal-event test through an accelerator high-energy proton comprises the steps that test samples are processed and the requirements of a signal-event test board and the requirements for selection of high-energy proton energy, the fluence rate and the fluence are satisfied. Single event upset of a large-scale circuit tends to be sensitive along with the increase of the integration degree and the reduction of the feature size. Single event upset can be generated through the method that a nuclear reaction of the proton occurs or the proton is directly ionized. An electronic system fault probably caused by single event upset happens to an on-orbit satellite. The method is used for conducting the device proton single event upset test on the ground. According to the method, the proton single event upset sensitivity of a key device for the satellite can be evaluated, proton single event upset sensitive parameters of the device can be obtained, a basis is provided for anti-radiation reinforcing design of the satellite, and the method for conducting the device proton signal-event test through the accelerator high-energy proton has important significance in the guarantee of the reliability of the new-generation satellite.

The invention provides a single event upset characteristic testing method for partially triple modular redundancy reinforced SRAM (static random access memory) type FPGA (field programmable gate array). The method comprises the following steps: irradiating a tested device at a set fluence rate, recording a single event error for once when the output characteristic of the device is not correct and the functions of the device do not return to normal within time T1 after the particle irradiation stops, and repeating the above steps for multiple times and then calculating a single even error section; reducing the particle fluence rate continuously till the single even error section becomes stable; and repeating the above steps under at least five different LET values in total.

The invention brings forward a method and device for measuring two-dimensional angle distribution of the radiation dose rate of a radioactive substance. The method comprises: a gamma camera detecting gamma photons incident from each direction of a defining object angle plane in an object area, and respectively recombining to form projection data and power spectrum data; reconstructing the projection data by use of an image reconstruction algorithm to obtain a radiation gamma image; based on this, obtaining the two-dimensional angle distribution of the fluence rate of the gamma photons incident from each direction in the object area; and according to incident photon energy, searching for corresponding conversion coefficients, and by use of the conversion coefficients, converting the two-dimensional angle distribution of the fluence rate of the gamma photons into the two-dimensional angle distribution of the dose rate of radiation of the radioactive substance to the position of the gamma camera. The measuring method provided by the invention realizes measurement of the two-dimensional angle distribution of the radiation dose rate of the gamma photons incident from the different directions in the object area by use of such devices as the gamma camera and the like.

A method for delivering photodynamic therapy (PDT) while performing dose metric monitoring and treatment feedback-driven control is presented. Photodynamic therapy is initiated with irradiation of light at a first irradiance. A set of fluorescence and reflectance spectroscopic measurements are taken at prescribed intervals during the therapy of the treatment region. Spectra are analyzed to determine dose metrics of the therapy such as fluorescence photobleaching of the sensitizer and blood oxygen status and optical properties of the treatment region. This information is then used to determine an optimal fluence rate given those parameters and the region is irradiated with a second irradiance. This process is continued until either the entire prescribed fluence is delivered to the region or a predetermined extent of photosensitizer bleaching is achieved.

The invention discloses a nuclear power plant integrated in-core instrumentation assembly. The in-core instrumentation assembly introduces an in-core from a top cover of a reactor pressure vessel, and comprises an upper shell located outside the reactor pressure vessel, a shell located inside the reactor pressure vessel, a plurality of neutron fluence rate measurers used for detecting axial power distribution of the in-core and a thermocouple used for measuring outlet temperature of the in-core; the neutron fluence rate measurers and the thermocouple are all mounted in the shell, and the shell is used for ensuring that the neutron fluence rate measurers and the thermocouple are not in contact with a primary circuit coolant. Compared with the prior art, the nuclear power plant integrated in-core instrumentation assembly provided by the invention introduces the in-core from the top cover of the reactor pressure vessel, and meets the design requirements of advanced reactors; moreover, simultaneous measurement on the outlet temperature of the in-core and the neutron fluence rate of the in-core can be realized, and the trepanning amount of the reactor pressure vessel is reduced, so that the design safety of the reactors can be improved.

The invention belongs to the field of reactor core power monitoring of reactors in nuclear power plants, and in particular, relates to data acquisition and processing system of reactor core neutron fluence rate. The system comprises core testing device and data processing device. The core testing device comprises multiple measuring cabinets and one synchronously shared cabinet. Measuring cabinetsand the synchronously shared cabinet are respectively connected to the mobile detector in core through the measuring pipe. Each measuring cabinet has a corresponding mobile detector and multiple mobile detectors are installed in different measuring pipes which are different from their neutron fluence rate. There are two data processors in the data processing device. One connects to the measuring cabinet containing core testing device to realize the acquisition of data. Real-time communication between the first and second processor is ensured. The second processor will carry out the real-time response to the signals collected by the first processor including test of the abnormal temporal logic signals and error correction for analog signals of neutron fluence rate.

Relating to the technical field of nuclear power, the invention provides a nuclear reactor core neutron and temperature detection device, and solves the technical problems of reducing the sensitivitydeviation and improving the service life. The device comprises a plurality of reactor core detection components installed in a pressure vessel, the reactor core detection components are evenly laid along the radial direction of the pressure vessel, and each reactor core detection component includes at least one armored nuclear grade thermocouple thermometer for monitoring the reactor core fuel assembly outlet coolant temperature and multiple vanadium self-powered neutron detectors for monitoring the nuclear reactor core neutron fluence rate, also the vanadium emitters of the vanadium self-powered neutron detectors have an equal length, and the vanadium self-powered neutron detectors are laid from the bottom up in order along the axial direction of the pressure vessel. The device provided by the invention is suitable for a pressurized water reactor nuclear power station reactor core instrument system.

A method for use in a computer system provides a dynamic, “self tuning” soft-error-rate-discrimination (SERD) method and apparatus. Specially designed SRAMs or other circuits are “tuned” in a manner that gives them extreme susceptibility to cosmic neutron events (soft errors), higher than that of the “regular” SRAM components, memory modules or other components in the computer system. One such specially designed SRAM is deployed per server. An interface algorithm continuously sends read/write traffic to the special SRAM to infer the soft error rate (SER), which is directly proportional to cosmic neutron flux. The inferred cosmic neutron flux rate is employed in a Poisson SPRT algorithmic approach that dynamically compensates the soft error discrimination sensitivity in accordance with the instantaneous neutron flux for all of the regular SRAM components in the server.

The invention relates to a thimble assembly of an in-core instrument for a nuclear power station. The thimble assembly comprises armored thermocouples, a header and neutron detectors, wherein at least one armored thermocouple and a plurality of neutron detectors are soldered and fixed together via the header; each neutron detector is a self-powered neutron detector composed of a transmitter, a collecting body, an insulator and a cable; the longest neutron detector of the plurality of neutron detectors has a length identical to the height of the whole reactor core; and the lengths of the rest neutron detectors gradually decrease at an equal interval on the base of the length of the longest neutron detector, or the neutron detectors are of a same length and axially distributed at an equal interval. The thimble assembly is simple and firm in structure and small in size and can adapt to complex environments in reactors. The thimble assembly is applicable to measurement of the outlet temperature of a reactor core in a nuclear power station and measurement of the neutron fluence rate of the core and has long service life.

The invention provides an SRAM type FPGA test method based on irradiation test environment simulation. Fault injection is performed on a circuit realized by adoption of an SRAM type FPGA, by continuous injection of single event upset faults of random addresses and random types into the circuit, influence of parameters of an incident particle LET value, fluence rate Flux and fluence Fluence on the circuit in a ground irradiation test is simulated, and effectiveness of circuit reinforcing design is quantitatively evaluated. The SRAM type FPGA test method provided by the invention can obtain a characteristic curve of changes of a dynamic upset section of the circuit with the LET value, thereby estimating an in-orbit failure rate.

The invention provides a method for testing single event upset characteristics of partialparts of triple modular redundancy static random access memory (SRAM) type field programmable gate arrays (FPGA). The method comprises the steps of irradiating a device to be tested under the preset fluence rate, recording one single-particle error when the output characteristic of the device is incorrect and functions of the device do not get right in time T1 for stopping particle beam irradiation, and calculating a single-particle error section after multiple repetition; continuously reducing the particle fluence rate until the single-particle error section tends to be stable; and providing another comparison device which is not subjected to triple modular redundancy fixing, irradiating the comparison device under the comparison fluence rate, calculating a single-particle error section, and then calculating the ratio of the single-particle error section of the comparison device to the single-particle error section of the device to be tested.

The invention relates to a cascade and point defect producing method based on charged particle irradiation, relates to the field of the space environment effect and aims to meet the research requirement for the displacement damage effect. The method comprises steps as follows: charged particles are selected; the unit time displacement damage absorbed dose D produced by the charged particles is calculated; D'(E) which is the displacement damage absorbed dose produced by one charged particle with the energy as E is calculated, and phi is the fluence rate; effective charged particles with D'(E) larger than a displacement defect producing threshold are selected; charged particles with D smaller than a point defect threshold are selected from the effective charged particles to serve as irradiation sources to produce point defects; charged particles with D larger than a cascade defect threshold are selected from the effective charged particles to serve as irradiation sources to produce point defects and cascade defects. The method is applicable to production of the cascade and point defects.

The invention provides a particle fluence rate selection method for a large scale integrated circuit accelerator single particle test. The particle fluence rate selection method for the large scale integrated circuit accelerator single particle test including the following steps: S1, judging whether the DICE design is adopted inside a large scale integrated circuit or not, S2, conducting high-fluence rate irradiation on the large scale integrated circuit according to the ASTMF 1192 standard code if the DICE design is adopted, S3, judging whether the TMR is adopted in the large scale integrated circuit or not according to the procedures used by the large scale integrated circuit if the DICE design is not adopted, S4, conducting low-fluence rate irradiation on the large scale integrated circuit if the TMR is adopted, S5, judging whether the EDAC is adopted in the large scale integrated circuit or not according to the procedures used by the large scale integrated circuit if the TMF is not adopted, S6, conducting the low-fluence rate irradiation on the large scale integrated circuit if the EDAC is adopted, and S7, conducting the high-fluence rate irradiation on the large scale integrated circuit if the EDAC is not adopted. Compared with the prior art that only the high-fluence rate irradiation is used, the particle fluence rate selection method for the large scale integrated circuit accelerator single particle test improves irradiation evaluation accuracy.

The invention relates to a method for signal compensation through prompt gamma signals of a self-powered detector. The method comprises the following steps that 1, neutron fluence rate distribution in a nuclear reactor is measured through the self-powered in-reactor detector; 2, the percent K of the gamma signals in signals collected by the self-powered in-reactor detector is determined; 3, the signals collected by the self-powered in-reactor detector are subjected to compensation, the self-powered in-reactor detector is a vanadium-based self-powered in-reactor detector, and the compensation function is shown in the specification, wherein T1/2 is the half-life period of an emitter material of the self-powered in-reactor detector, and S is a Lapras operator. The collected signals are subjected to compensation through the compensation function, and therefore the precision degree of axial power deviation measurement on the compensated signals can be improved.

The invention discloses a fission neutron converter. The fission neutron converter comprises an inner sleeve and an outer sleeve coaxially sleeved with the inner sleeve, wherein an upper grid plate and a lower grid plate are respectively mounted at two end parts between the inner sleeve and the outer sleeve, and cross-shaped fuel rods are mounted between the upper grid plate and the lower grid plate. According to the fission neutron converter disclosed by the invention, the bottleneck problem of material irradiation is solved by adequately utilizing technical conditions of the convention research reactor, the twofold effect can be achieved with half effort, and the current problems that on the one hand, the advanced research reactor cannot be built in one day, and on the other hand, a large amount of in-service research reactors are still operated are solved; by utilizing the cross-shaped fuel rods made of high-fission-density fuels, the fluence rate of local fast neutrons of a reactor core is substantially improved under a condition that the physical and thermotechnical safety of an HFETR (High Flux Engineering Test Reactor) is met, so that the technical potentials of the HFETR effectively are developed, and furthermore, the irradiation cost of materials is saved.