14 results about "Neutron irradiation" patented technology

This invention discloses a method for producing radioactive isotopes in the core of an advanced high-temperature reactor using a spherical target. This invention overcomes the limitations of using neutron irradiation channels or fuel-related components of nuclear reactors, such as conditioning rods in heavy water reactors and combustible poison rods in pressurized water reactors, to produce radioactive isotopes. It sets a precedent for the mass production of radioactive isotopes using the core of a nuclear reactor, and has significant strategic implications for exploring high-value applications of commercial advanced high-temperature reactors to reduce operating costs and mass-produce radioactive isotopes, including the strategic isotope tritium.

The application belongs to the technical field of gallium nitride substrate preparation, and particularly relates to a preparation method of n-type gallium nitride self-supporting substrate and a heavily doped GaN substrate and application. The preparation method of the n-type gallium nitride self-supporting substrate comprises the following steps: (1) sequentially epitaxially growing a buffer layer and a gallium nitride thick film on an original substrate; (2) peeling off the gallium nitride thick film to obtain a gallium nitride peeled sheet; (3) according to a germanium atom theoretical doping concentration of the gallium nitride peeled sheet, performing neutron irradiation treatment on the gallium nitride peeled sheet to obtain a germanium-doped gallium nitride peeled sheet; and (4) performing annealing treatment on the germanium-doped gallium nitride peeled sheet to obtain an n-type gallium nitride self-supporting substrate. The n-type gallium nitride self-supporting substrate obtained by the preparation method has a carrier concentration of 5x10 19 / cm 3 Without exogenous silicon or germanium dopants, the n-type gallium nitride self-supporting substrate obtained by the preparation method can be doped after the gallium nitride peeled sheet is formed, and the doping amount and doping concentration of the germanium element can be accurately controlled, which is suitable for large-scale production.

This invention discloses a cerium-doped InP-based single-photon avalanche detector for space communication and its fabrication method. The detector's epitaxial structure, from bottom to top, includes a substrate, an N-type buffer layer, an absorption layer, a band transition layer, an N-type charge layer, an intrinsic multiplication layer, an intrinsic InP layer, and a cerium-doped P-type contact layer. The core innovation lies in the dual radiation-resistant design of the Ce-doped P-type contact layer and the Ce-doped modified stacked passivation film. The fabrication method involves MOCVD epitaxial growth, spin-coating source diffusion to prepare the P-type contact layer, ICP etching and wet repair, magnetron sputtering doping, and electrode fabrication. This invention utilizes Ce's unique electronic structure to suppress radiation-induced defects and combines this with an SACM structure to optimize the electric field distribution, achieving low dark count rate, high detection sensitivity, and excellent neutron radiation resistance. The process is compatible with existing semiconductor production lines and is suitable for wafer-level mass production, meeting the high-reliability single-photon detection requirements of aerospace missions such as space laser communication and quantum key distribution.

This invention discloses a high-boron-loading manganese-based boron drug for BNCT diagnosis and treatment, its preparation, and its application, belonging to the fields of biomedicine and nuclear medicine. The boron drug structure is shown in general formula 7, with manganese porphyrin as the core skeleton. A benzene ring side chain at the meso position of the porphyrin ring is connected to a boron-10-containing catechol borate ester group via an amide bond. All boron atoms are boron-10 isotopes. The preparation method includes: first constructing the manganese porphyrin skeleton through condensation, cyclization, and metal coordination reactions; then independently preparing boron source units; and finally obtaining the target product through amide bond coupling. This boron drug possesses high boron-10 loading, efficient blood-brain barrier penetration, and excellent MRI imaging performance, enabling real-time and precise monitoring of boron drug distribution in vivo. The quantitative correlation between imaging signals and boron concentration guides the timing of neutron irradiation, integrating MRI tracing and BNCT treatment, effectively solving the problems of low boron loading, inability to penetrate the blood-brain barrier, and difficulty in real-time monitoring of in vivo distribution in existing boron drugs.

This invention relates to a nuclear-targeted multimodal imaging diagnostic probe with BNCT therapeutic efficacy, its preparation, and its application, belonging to the fields of biomedicine and nuclear medicine technology. This boron drug contains... 10 Using acetylacetone difluoroborate as the parent nucleus, this invention endows the tumor with nuclear targeting ability by introducing N- or S-containing heterocyclic structures, while utilizing its conjugated structure to provide fluorescence / photoacoustic dual-modal imaging functionality. Based on this, the invention achieves three core functions: first, through fluorescence / photoacoustic dual-modal imaging, it enables the visual localization and real-time monitoring of tumor sites; second, by leveraging the binding of nuclear targeting groups to nuclear DNA / RNA, it... 10 B is precisely delivered into the nucleus, significantly improving the killing efficiency of BNCT; thirdly, thermal neutron irradiation is performed under imaging guidance, triggering... 10 The B(n,α)⁷Li nuclear fission reaction ultimately enables high-precision integrated diagnosis and treatment. This invention also discloses a method for preparing this probe, which has promising clinical application prospects.

The application relates to light-absorbing glass for preparing liquid scintillation capillary arrays and a preparation method and application thereof, which comprises the following components in terms of mass percentage of oxides: SiO2: 70-78%; Al2O3: 3-6%; B2O3: 5-12%; Mn2O3: 0.5-1.5%; Fe2O3: 0.2-0.7%; CuO: 0.1-0.3%; CoO: 0.1-0.3%; ZnO: 1-3%; CeO2: 0.2-1%; the total content of K2O and Na2O is 5-8%; and the total content of KHF2 and K2SiF6 is 0.8-1.5%. The light-absorbing glass for preparing liquid scintillation capillary arrays has high absorption performance to light in the wavelength range of 375-700 nm, excellent anti-crystallization performance and neutron irradiation resistance, and a softening temperature matched with low-refractive-index tube material glass of the liquid scintillation capillary array, and is suitable for preparing the liquid scintillation capillary array.

The application discloses a neutron irradiation sample box convenient for remote operation and a dismounting tool thereof, and belongs to the cross field of nuclear science and technology application and equipment manufacturing. The sample box comprises a sample cover, a sealing sheet, a sample inner grid and a cavity. The sample cover is in threaded connection with the cavity. The sealing sheet is sealed by plastic deformation. The sample inner grid is divided into partition compartments for placing samples. The dismounting tool comprises an installation base, a screwing handle, a lower jaw, a circular arc knife edge, a sample box separation nut and an arched sample box positioning block and the like. The sample box is convenient for remote operation of adding and removing samples by special design. The non-welding sealing is adopted to guarantee sample irradiation conditions. The dismounting tool can be remotely operated in the whole process. The application further increases innovative features such as radiation-resistant adhesive, a pressure sensor and a fine adjustment device, improves sealing stability and operation accuracy, and solves the problems of inconvenience in remote operation, sealing and sample adding and removing of the traditional sample box.

The invention provides a particle discharging device and method for a Tokamak divertor area. The device comprises an adsorbent pump unit arranged in a divertor area and a gas channel structure communicated with the divertor area, and is used for capturing and discharging neutral particles generated by interaction of plasma and divertor components. The adsorbent pump unit is made of a non-evaporation type adsorbent material, has high adsorption capacity on hydrogen and isotopes thereof, can keep stable structure and working performance under the condition of high temperature, and is suitable for a high-heat-load and high-particle-flux operating environment in a divertor area. The in-situ air exhaust of the neutral particles is realized in the divertor area, so that the transport path of the particles is shortened, and the response speed and efficiency of particle discharge are improved. Meanwhile, the particle discharging device has large air extraction capacity and effective extraction speed, is suitable for tritium-related application scenes and operating environments with neutron irradiation, and has good engineering application prospects.

The present application relates to a kind of NAD (P) H response type diagnosis and treatment integrated boron medicine and its preparation method, the boron medicine with 10 B acetylacetone difluoroboric ester as mother nucleus, by introducing the cell nucleus target ability of N-containing or S-containing heterocyclic structure, simultaneously introduce the response unit that can specifically respond to high expression NAD (P) H in tumor microenvironment, activate fluorescence / photoacoustic dual-mode imaging signal, realize the visual positioning of tumor site.On this basis, the present application realizes three big core functions: one is through NAD (P) H response point light imaging, effectively reduce background signal interference;Two is by means of N or S atom and the combination of cell nucleus DNA / RNA, will 10 B be accurately delivered to nucleus, significantly improve BNCT killing efficiency;Three is under the guidance of imaging, thermal neutron irradiation is carried out, triggers 10 B (n, α) 7 Li nuclear fission reaction, finally realizes high-precision diagnosis and treatment integration.The preparation method of the boron medicine is also disclosed, can be used for preparing malignant tumor diagnosis and treatment drug, has good clinical application prospect.

An electrical cable for use as a substitute for mineral-insulated cables in nuclear facilities is described herein. The cable may include at least one conductor, insulation, a jacket, and an armor shell. In some embodiments, the conductor may comprise a stranded conductor of one of various grades. The insulation may comprise phlogopite or muscovite mica tape that may be helically or longitudinally applied in overlapping concentric layers around at least one conductor. The jacket may comprise a woven glass braid applied over insulation surrounding one or multiple conductors. The armor may comprise hermitically sealed metallic armor applied around the other components of the cable, thereby forming an exterior of the cable. The inorganic materials utilized may be configured to limit the creation of adverse and / or undesirable elements instigated by transmutation from neutron irradiation exposure.

Disclosed herein are devices and methods for measuring tritium production. For example, disclosed herein are devices comprising a first layer and a second layer, each comprising a detection material, and the thickness the layers being configured such that tritium cannot pass therethrough. When a lithium composition is substantially contained within a chamber formed by the first and second layers, and a neutron irradiation source irradiates the lithium composition disposed within the chamber; then the device produces tritium within the chamber that diffuses to the first layer and / or the second layer, and the tritium interacts with the first detection material and / or the second detection material to thereby form a signal that is detected and analyzed to determine a property of tritium, such as the presence or absence of tritium production, the amount or concentration of tritium produced, the rate of tritium production, or a combination thereof.

The present application relates to the technical field of neutron activation and discloses a power supply based on neutron activation and a preparation method thereof, the power supply comprising a to-be-activated radioactive source layer and a transduction layer, the to-be-activated radioactive source layer having to-be-activated particles capable of being activated into radioactive particles by neutrons, and the transduction layer being arranged on the to-be-activated radioactive source layer in the thickness direction of the to-be-activated radioactive source layer. The power supply can overcome the technical problem of how to avoid radiation hazards in the process of preparing the power supply, a non-radioactive (non-source) power supply is prepared first, and then activated into a source battery through neutron irradiation, so that the risk of radioactive substances can be avoided.