54results about How to "Large atomic number" patented technology

The present invention provides a phase change memory cell comprising (Ge_ASb_BTe_C)_1−x(R_aS_bTe_C)x solid solution, the solid solution being formed from a Ge—Sb—Te based alloy and a ternary metal alloy R—S—Te sharing same crystal structure as the Ge—Sb—Te based alloy. A nonvolatile phase change memory cell in accordance with the present invention provides many advantages such as high speed, high data retention, and multi-bit operation.

The present invention provides a new scintillator, cerium bromide (CeBr₃), for gamma ray spectroscopy. Crystals of this scintillator have been grown using the Bridgman process. In CeBr₃, Ce³⁺ is an intrinsic constituent as well as a luminescence center for the scintillation process. The crystals have high light output (˜68,000 photons/MeV) and fast decay constant (˜17 ns). Furthermore, it shows excellent energy resolution for γ-ray detection. For example, energy resolution of <4% (FWHM) has been achieved using this scintillator for 662 keV photons (¹³⁷Cs source) at room temperature. High timing resolution (<200 ps-FWHM) has been recorded with CeBr₃-PMT and BaF₂-PMT detectors operating in coincidence using 511 keV positron annihilation γ-ray pairs.

The present invention concerns very fast scintillator materials comprising lutetium iodide doped with Cerium (Lu_1-xI₃:Ce_x; LuI₃:Ce). The LuI₃ scintillator material has surprisingly good characteristics including high light output, high gamma ray stopping efficiency, fast response, low cost, good proportionality, and minimal afterglow that the material is useful for gamma ray spectroscopy, medical imaging, nuclear and high energy physics research, diffraction, non-destructive testing, nuclear treaty verification and safeguards, and geological exploration. The timing resolution of the scintillators of the present invention provide compositions capable of resolving the position of an annihilation event within a portion of a human body cross-section.

The invention belongs to the field of high performance scintillant materials and high-energy ray detection and discloses an application of a compound as a scintillant material and a preparation methodthereof. The compound has a chemical general formula AB2X3, wherein A is a monovalent alkali metal cation, B is a monovalent transitional metal cation and X is a monovalent halogen anion. The preparation method comprises the following specific step of preparing the compound with the chemical general formula AB2X3 based on an anti-solvent devitrification method, a cooling devitrification method, afused salt mixing method or a pulling method by taking AX and BX, the molar ratio of which is 1: 2, as raw materials. By regulating components of the compound, a novel scintillant material with the chemical general formula AB2X3 is obtained. The scintillant material has the characteristics of being non-toxic, stable, simple in preparation method and high in photoyield. As the novel scintillant, the material has a huge potential in the field of high energy detection and shows an application prospect of large-scaled industrial production.

The invention relates to a solid organic scintillator comprising a polymeric matrix in which there are dispersed one or more fluorophore compounds and one or more chemical elements having an atomic number ranging from 40 to 83, characterized in that said scintillator has a weight content of said chemical elements of at least 5% by weight relative to the total weight of the scintillator, and in that the scintillator emits an emission spectrum comprising an emission peak at a wavelength of at least 550 nm.

The present invention discloses a schottky type room temperature nuclear radiation detector which comprises a schottky structure formed by the GaN substrate, a schottky electrode and an ohmic electrode, and the invention that the following characters: the GaN substrate is a thick film structure with thickness 100um to 200um, the schottky electrode and ohmic electrode are respectively arranged at surface at two sides of the GaN substrate. As the GaN material used in the invention has the following excellent capabilities of broad forbidden band width, high resistivity, large atomic number, better covalent bond combination, high melting point, high breakdown electric field, anti-corrosion and radiation resistance, the prepared room temperature nuclear radiation detector has excellent room temperature sensitiveness, detection efficiency and stability, and is more suitable for the detecting field of the high-radiation field. At the same time the manufacturing technique is simple and cost is low, and the invention is suitable to be industrially generalized.

The invention discloses a U-W-N ternary thin film and a preparation method and application thereof, belongs to the technical field of laser fusion engineering, and particularly relates to a U-W-N ternary thin film with black cavity dispersion reduction and protection effects and a preparation method and application of the U-W-N ternary thin film. The preparation method and application of the U-W-Nternary thin film aim to solve the problems that a structure layer of an existing uranium black cavity is complex, the regulation and control range of the N content in a UN<x> dispersion reduction/protection layer is limited, the stimulated Brillouin scattering inhibition capacity is limited, and M-band hard X rays of an Au protection layer and superheated electrons are prone to exciting. The mass fraction of N in the U-W-N ternary thin film is x%, x is larger than 0 and smaller than or equal to 66.7%, the mass fraction of W is y%, y is larger than 0 and smaller than or equal to 10%, and thebalance U. The preparation method comprises the steps that a direct-current reactive magnetron sputtering co-deposition method is adopted, N2 serves as reaction gas, magnetron sputtering deposition isconducted on a U target and a W target through a direct-current power source, and the U-W-N ternary thin film is obtained. And the U-W-N ternary thin film is applied to the black cavity as a dispersion reduction/protection layer.

The invention belongs to the field of atom cooling and capturing technology, and provides a method and a device used for preparing an ultra long type cold atomic cloud asymmetric two-dimensional magnetic optical trap. The method comprises following steps: 6 cooling light beams enters into a MOT glass cavity, and meet at a point, the 6 cooling light beams are divided into three pairs, and the two light beams in each cooling light beam pair are designed to be correlation overlapped, the first cooling light beam pair is designed to travel along the X axis direction, and the second cooling light beam pair and the third cooling light beam pair are designed in the Y/Z plane with an angle equal to or larger than 120 DEG; a first rectangular coil pair parallel to the Y/Z plane and a second rectangular coil pair parallel to be X/Z plane are arranged at the surrounding of a window of the MOT glass cavity, the length of the second rectangular coil pair is designed to be 1.5 times of the length ofthe first rectangular coil pair, and the first rectangular coil pair and the second rectangular coil pair are all anti-Helmholtz coils. The method and the device can be used for preparing high atom number and high optical thickness ultra long cigar-shaped cold cesium atom cloud, and providing high quality experiment mediums for quantum coherence effect, quantum storage, and quantum precision measuring researches.

The invention relates to nuclear power plant containment concrete. The concrete consists of the following components in parts by mass: 130-200 parts of cement with strength of 52.5 or 42.5, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, 600-800 parts of nickel slag, 600-800 parts of barite, 200-400 parts of limonite, 100-300 parts of ceramsite, 20-50 parts of lead fibers, 130-160 parts of water, 4-6 parts of a water reducing agent and 4-6 parts of an early strength agent. After 28 days of curing of the concrete, the inner surface of the concrete is coated with a layer of anti-radiation coating. The nuclear power plant containment concrete provided by the invention has a good anti-radiation property, can well shield alpha, beta and gamma rays and neutronrays, and has good crack resistance, high-temperature resistance and durability, and simultaneously solid wastes such as nickel slag, glass powder and the like are utilized, so that the problems of resource waste and environmental pollution are solved to a certain extent.

An energy cell, employed as a passive energy source, takes advantage of the differing electrical properties of metals to produce an induced electromagnetic force charge when exposed to dosages of high energy photons such as x-ray or gamma rays.

The invention provides a chemical-resistant multi-layer radiation-proof glove which is of a multi-layer structure and comprises at least one neutron protective layer, at least one X-ray and gamma-rayprotective layer and at least one polyvinyl alcohol layer, and the polyvinyl alcohol layer is a middle layer. The chemical-resistant multi-layer radiation-proof glove has excellent anti-radiation capability and radiation aging resistance, can effectively protect the radiation of X-rays, gamma-rays, neutrons, deuterium, tritium and the like, and can also effectively protect organic solvents and other chemicals, so that the service life of the radiation glove is greatly prolonged; therefore, the life health of nuclear industry employees can be better protected.

The invention discloses a neutron deceleration composite material. The neutron deceleration composite material comprises a mixed material, a material which accounts for 0.1-5% of the weight of the mixed material and contains a 6Li element, and Cu which accounts for 0.1-5% of the weight of the mixed material, and the mixed material comprises one or a mixture of more of Al, MgF2 and AlF3; the mixed material comprises the following components in percentage by mass: 10-95% of pure aluminum powder, 20%-80% of aluminum fluoride powder, 0.1%-15% of magnesium fluoride powder; the material containing the < 6 > Li element is < 6 > LiF powder; the mixed material further comprises pure magnesium powder, and the mass percent of the pure magnesium powder is 0.1-5%. The radioactivity of the material can be attenuated to an exemption level or below within a short time when the material is decommissioned at the last stage of the device or equipment, and the neutron deceleration composite material has obvious advantages in the aspects of radioactive waste disposal method and economy.

An energy cell, employed as a passive energy source or a detector for sensing high energy photons, takes advantage of the differing electrical properties of metals to produce an induced electromagnetic force charge when exposed to dosages of high energy photons such as x-ray or gamma rays.