Abstract:
A neutron measuring method is provided. The method includes utilizing a thermoluminescent crystal (102) in a thermoluminescent dosimeter (101) to emit thermoluminescence or scintillation light, wherein the thermoluminescence is emitted when the thermoluminescent crystal (102) absorbs and stores ionizing radiation emitted by a metallic body (110) that has been activated and subsequently releases the stored ionizing radiation in the form of the thermoluminescence when heated, and wherein the scintillation light is emitted when the thermoluminescent crystal (102) converts the ionizing radiation emitted by the metallic body (110) that has been activated into the scintillation light; using a photodetector (103) to measure intensity of the thermoluminescence or the scintillation light; and calculating neutron intensity at which the metallic body (110) is located based on the measured intensity of the thermoluminescence or the scintillation light.
Abstract:
A neutron dose measurement method and apparatus. The neutron dose measurement method comprises: determining a unit to be corrected that corresponds to a dose monitoring system (S10); on the basis of the number of rays emitted, after neutron activation, by a nonmetal unit to be activated, and the unit to corrected that corresponds to the dose monitoring system, determining a first correction factor (S20); and correcting the dose monitoring system on the basis of the first correction factor, so as to determine a real-time neutron dose of a patient (S30). By means of the present application, a first correction factor is determined to correct the sensitivity of a dose monitoring system, so as to determine a real-time neutron dose of a patient, so as to prevent a measurement error caused by a sensitivity reduction or a position change in the dose monitoring system, thereby improving the accuracy and reliability of a measurement result.
Abstract:
The present invention provides a method for forming a sensitive film for neutron detection, wherein the sensitive film is formed by electrophoresis coating, the liquid used for electrophoresis coating includes neutron sensitive material, electrophoresis paint and deionized water, and the neutron sensitive material is 10 B single substance, 10 B compound or mixture containing 10 B. The sensitive film for neutron detection has high detection efficiency because of the high content of 10 B. The sensitive film for neutron detection has uniform and stable film thickness, and excellent consistency. The production efficiency and the cost of the sensitive film are improved.
Abstract:
A long-lifespan in-core instrument having an extended lifespan due to an enhanced combustion lifespan of an emitter according to the present invention comprises: a central tube; an outer sheath tube distanced from the outer circumferential surface of the central tube; self-powered neutron detectors placed between the central tube and outer sheath tube, and each comprising an emitter of a material having a reaction cross section with neutron that is comparatively smaller than that of rhodium; a background detector for compensating for the background noise signal; core exit thermocouples for detecting the core exit temperature; and filler wires filling in the space between the self-powered neutron detectors, background detector and core exit thermocouples, and as such, the present invention can markedly reduce the amount of spent in-core instrument waste, which is high-level radioactive material, and thus can contribute in securing a utility space for the high-level waste material, as well as in reducing radiation exposure of the nuclear power plant personnel.
Abstract:
A method for monitoring the unknown contents in a volume comprises the steps of sending gamma radiation and/or fast neutrons emerging from said volume through a measuring volume (12) of at least one radiation detector (10), said measuring volume (12) containing a noble gas or a mixture of noble gases; counting the photons generated within said measuring volume (12) by an interaction (18) of the gamma radiation and/or fast neutrons with the noble gas or noble gases of the measuring volume (12) by means of photon counters (15, 16); deriving from the output of said photon counters (15, 16) a spectrum of the radiation passing through the measuring volume, wherein neutrons and gamma rays are discriminated by their different pulse shapes; and processing said derived spectrum to gain information about the unknown contents in said volume.
Abstract:
A method for detecting a neutron includes providing a first voltage to an input electrode of a microchannel plate, providing a second voltage to an output electrode of the microchannel plate, the second voltage being more positive than the first voltage, measuring a signal on the output electrode, and detecting a neutron based on a comparison of the signal at the output electrode with a baseline value.
Abstract:
Provision is made in a method and a device for detecting elementary particles such as for example protons, ions, electrons, neutrons, photons or the like in a detector (1), wherein a charge pulse is generated in the detector (1) when a particle passes through the detector (1) and every charge pulse is subsequently converted into an electric signal (3) and the signal is indicated and/or recorded in particular after amplification, for individual signals to be amplified in a first, fast amplifier (10) and/or in each case a plurality of signals to be integrated in a second, slow amplifier (12), as a result of which it becomes possible for individual particles to be detected and in particular at increased signal or count rates for an integration thereof to be provided.