32 results about "Equivalent dose" patented technology

The invention discloses a ship reactor shielding design optimization method based on a neural network and a genetic algorithm. A Monte Carlo method is used for simulating and calculating the reactor neutron and photon transport process; an MCNP (Monte Carlo N Particle Transport Code) program is used for carrying out simulation and calculation on a ship reactor layered shielding model; a neutron and photon flux after the reactor shielding is obtained; the total equivalent dose is worked out; a topological structure of a BP (Back Propagation) neural network is determined according to the input parameter number n1 and the output parameter number n2 of a sample; an adaptation degree function of the genetic algorithm is determined according to a reactor shielding problem objective; the recommended adaptation degree function is selected; and the strong optimization capacity of the genetic algorithm is used and is mutually coupled with the neural network to find the optimum shielding parameter. The ship reactor shielding design optimization method has the advantages that the high fitting capability of the neural network is used; the time consumption of the MCNP program in the particle transport process is reduced; the good optimization capacity of the genetic algorithm is used; and the optimum shielding parameter can be found in few iteration steps.

A lightweight neutron remmeter for measuring neutron equivalent dose with a response range from the thermal energy levels to around 14 MeV is achieved using a center BF₃ proportional neutron detector moderated by enclosure within a cylindrical center tube and two adjacent BF₃ proportional neutron detectors. A cylindrical hydrogenous material covered by a boron loaded rubber wrap moderates the center detector within the center tube. The adjacent neutron detectors are uncovered. In this manner the center detector responds to fast neutrons and the over response to thermal and intermediate energy neutrons is corrected by the adjacent neutron detectors readings and an algorithm implemented by a RADIAC.

The invention discloses a method for reducing the radiation dosage, and the method comprises the steps: acquiring first image data related to an ROI (region of interest) of a first object, wherein thefirst image data is corresponding to a first equivalent dosage, and the first image data may be acquired by a first device; obtaining a noise reduction model associated with the first image data anddetermining second image data corresponding to the second equivalent dosage based on the first image data and the noise reduction model, wherein the second equivalent dosage is greater than the firstequivalent dosage. In some embodiments, the method may further comprise the steps: determining information related to the ROI of the first object based on the second image data, and recording information related to the ROI of the first object. The present application converts low dosage images into high dosage images through a noise reduction model, and avoids exposure of the patient to excessiveradiation while obtaining equal or higher quality images.

The invention provides a method of expressing an exogenous nucleic acid in a mammal. The method comprises slowly releasing into the bloodstream a dose of replication-deficient or conditionally-replicating adenoviral vector having reduced ability to transduce mesothelial cells and hepatocytes. The normalized average bloodstream concentration of the adenovirus over 24 hours post-administration is at least about 1%. Alternatively, the normalized average bloodstream concentration over 24 hours post-administration is at least about 5-fold greater than the normalized average bloodstream concentration for an equivalent dose of a wild-type adenoviral vector. A method of destroying tumor cells in a mammal also is provided, as is a replication-deficient adenoviral vector comprising a serotype 5 or serotype 35 adenoviral genome with a serotype 41 fiber protein, wherein the replication-deficient adenoviral vector exhibits reduced native binding to integrins.

The invention consists of an area dosimeter for measuring the ambient equivalent dose (H*(10)) of photon radiation with a diffuser, a detector card with at least one pair of detection elements, preferably LiF-chips,

• • whereby the first of the two detection elements is positioned between two filters in order to spectrally filter the photon radiation,
  • whereby the second of the two detection elements is not positioned between such filters as those of the first detection element, in order that the photon radiation arriving at the second detection element have a different spectral distribution as the spectrally filtered photon radiation arriving at the first detection element. The two measurement values are used to obtain a weighted sum in order to achieve an optimized response characteristic, in particular in the range below 30 keV and if applicable in the range above 1.3 MeV.

The invention discloses a portable energy adjusting device for equivalent dose detection of a heat energy-100 MeV neutron, which comprises an inelastic scatterer, a fast neutron moderator, an energy adjustor and a thermal neutron detector. The whole device takes the shape of a ball, the thermal neutron detector is arranged at the center of a ball body and coated with the spherical fast neutron moderator; the fast neutron moderator is coated with a spherical ultrafast neutron inelastic scatterer; and the energy reaction adjustor is positioned between the fast neutron moderator and the fast neutron inelastic scatterer. The portable energy adjusting device has the advantages of compact structure and light weight and can improve the reaction of a high-energy neutron by about 30 percent as well as the sensitivity of the neutron by about 18-40 times through experimental evidence compared with the prior art.

The is described a process for determining a validated Reduction Equivalent Dose for reducing the concentration of a target contaminant contained in a fluid in a radiation fluid treatment system. In one embodiment, the process comprises the steps of: (a) determining a short wavelength Reduction Equivalent Dose for the target contaminant or a challenge contaminant in a first region of the electromagnetic spectrum having a wavelength of less than or equal to about 240 nm; (b) determining a long wavelength Reduction Equivalent Dose for the target contaminant or a challenge contaminant in a second region of the electromagnetic spectrum having a wavelength of greater than about 240 nm; and (c) summing the short wavelength Reduction Equivalent Dose and the long wavelength Reduction Equivalent Dose to produce the validated Reduction Equivalent Dose for the target contaminant. In a preferred embodiment, the present invention provides a useful approach for determining the relevant Reduction Equivalent Dose (RED) for Cryptosporidium disinfection and accomplishes this by using the discovered relation between the short wavelength sensor signal and the short wavelength RED, and subtracting the short wavelength RED from the RED determined using a challenge microbe with synthetic lamp sleeves, to obtain the long wavelength RED applicable to Cryptosporidium disinfection. In a bioassay, one would only need the short wavelength sensor reading and the challenge microbe RED using synthetic lamp sleeves to determine the applicable RED, once the relationship between the short wavelength sensor reading and the short wavelength RED was established.

The invention discloses a novel mixing glue barrel which comprises a glue barrel main body and a barrel plug; the glue barrel main body comprises a barrel body and a glue outlet nozzle which are fixedly connected; the barrel body is in the shape of hollow cylinder with a bottom-end opening; the glue outlet nozzle is positioned on the center of the top end of the barrel body; a partition is arranged inside the glue barrel main body for dividing the barrel body and the glue outlet nozzle into two symmetrical cavities; sections of the two cavities in the barrel body are in the shape of two circles which are bilaterally symmetrical; and the barrel plug is separately arranged in the semicircular cavities of the barrel body. The novel mixing glue barrel disclosed by the invention is simple in structure; the single cylindrical barrel body is divided into two cavities through one partition, and a mixture of a component A and a component B is respectively placed in the two cavities, an opening of the glue outlet nozzle is opened through a pair of scissors first, and then the barrel plug is extruded through a glue gun, so that the mixture of the component A and the component B can be extruded with equivalent dose.

The invention discloses a space charged particle telescope based on cadmium zinc telluride. An opening is formed in the top end of an outer cover of the space charged particle telescope, a mounting base is arranged in the outer cover, a Si semiconductor detector, a first CZT detector and a second CZT detector are arranged on the mounting base, and the Si semiconductor detector and the first CZT detector form a first delta EE detector system; and the first CZT detector and the second CZT detector form a second group of delta EE detector systems, and the first delta EE detector system and the second delta EE detector system are matched to respectively measure charged particles with different energies. According to the invention, charged particles, thermal neutrons, gamma rays and other components in a space environment can be measured. The telescope can effectively measure information such as energy transfer linear density spectrum (LET), equivalent dose, charged particle energy spectrum, total dose, dose rate and the like of charged particles in space, has very important significance for astronaut radiation risk assessment, and can improve the resolution of the particle energy spectrum and enhance the particle identification capability compared with a traditional scintillation crystal system.

The invention discloses a calculation method for a risk control value of arsenic in soil and application thereof. The calculation method comprises the following steps: S1, calculating equivalent doses of various approaches based on different media; s2, calculating a soil risk control value of each approach based on an equivalent dose; and S3, calculating a soil total risk control value Cs based on the equivalent dose. According to the calculation method, the basis is provided for formulating the soil remediation target value of the arsenic-contaminated site in China based on the equivalent doses of different media, and excessive remediation of the contaminated site is avoided.