11 results about "Deuterium" patented technology

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The present disclosure relates to a method for analyzing and predicting deuterium substitution rates of a deuterium-substituted sample using a mass spectrometry spectrum of the deuterium-substituted sample.

The invention discloses a method for realizing a compact pulse neutron source. According to the method, a vacuum upper cover plate of an ion source component is located at a suspension potential, and a 2KV pulse voltage is applied to the vacuum upper cover plate. According to the pulse type compact deuterium-deuterium neutron generator device, the ion source part is subjected to high-voltage suspension isolation, the pulse voltage is applied to the ion source part, and the extraction and turn-off of the ion beam are directly controlled, so that pulse type neutron output is realized, the structure is simple and compact, and the manufacturing cost is low.

The application discloses a neutron tube deuterium-tritium reservoir, a nickel tube is arranged in the nickel cylinder body, through holes are arranged on the nickel tube, a hydrogen absorption coating is arranged on the inner and outer surfaces of the nickel tube and the side surface of the nickel cylinder body, ceramic tubes are arranged between the nickel cylinder body and the nickel tube and in the nickel tube, sealing openings are arranged at the bottom of the nickel cylinder body and the nickel tube, insulating sealing ceramic glue is arranged at the sealing openings, and the two ends of the ceramic tubes pass through the insulating sealing ceramic glue at the bottom of the nickel tube and the bottom of the nickel cylinder body respectively; the internal double-layer structure greatly increases the storage capacity of the hydrogen absorption material for deuterium-tritium gas, the double-layer spiral ceramic tubes are heated to cooperate with the double-layer structure, the hydrogen absorption material heating surface of the device can be increased, the size of the heating current is controlled to realize accurate control of the deuterium-tritium gas release amount, the closed reservoir made of alloy metal nickel avoids exposing the hydrogen storage material, has the function of hydrogen permeation, and guarantees the deuterium-tritium release.

A quasi-pulsed FRC deuterium-deuterium fusion reactor and its self-sustaining nuclear fuel cycle steady-state power generation method are disclosed. The reactor comprises a linear vacuum chamber, an FRC plasma formation zone, a collision fusion zone, a conical transition section, a plasma formation coil, a fast compression coil, a magnetic mirror coil assembly, a deuterium-tritium feeding system, a zoned vacuum pumping system, and a pulsed power control system. The magnetic mirror coil assembly is located near the collision fusion zone in the conical transition section. Within a single pulse cycle, it sequentially executes four functional modes: compression assistance, magnetic mirror reflection, magnetic bottle confinement, and recovery attenuation. During the recovery attenuation mode, it is reused as a direct energy conversion induction coil. The operation mode employs a trace amount of tritium to catalyze deuterium-deuterium fusion. Tritium and helium-3 are confined to participate in the secondary reaction through magnetic mirror confinement. Between pulses, the difference in chemical adsorption of tritium and the difference in cryogenic condensation of helium-3 are utilized to achieve selective recovery of the two components, forming a quasi-pulsed self-sustaining operation. The power is then converted into steady-state electrical power and connected to the grid via a rectification-storage-inverter system, realizing the internal recycling of tritium and helium-3.

In an inductively coupled high-density plasma chamber, a film is modified to include deuterium. Chamber hardware design enables tunability of deuterium concentration uniformity throughout the film across a substrate. Fabrication of solid state electronic devices includes integrating process flows to modify a film that is substantially hydrogen and deuterium free to include deuterium.

The application discloses a firecracker type cyclotron collision beam nuclear fusion power generation device and a power generation method. + The nuclear fusion power generation device adopts double-beam central collision dissociation, D2 The dissociation rate is much higher than that of a traditional single beam dissociation mode, and the deuterium nuclear capture amount and the fusion probability are greatly improved; double-path energy extraction and firecracker type multi-heap relay scheme design solve the unstable problem of fusion energy output and meet the continuous power supply demand; the compact cyclotron and the modularized vacuum cavity design are adopted, so that the device volume is smaller than that of a traditional magnetic confinement fusion device, and the beam parameters obtained by the cyclotron are superior to those of a linear acceleration beam of a traditional Migma device; the method is high in safety, the ions in the device are highly ordered, the fusion neutron flux is low and is completely absorbed, and there is no risk of radioactive leakage, and there is no long-term radioactive waste after the device is decommissioned.

The invention discloses a device and method for testing the oxidation resistance of a hydrogen and deuterium storage material, and the device for testing the oxidation resistance of the hydrogen and deuterium storage material comprises a closed box, supporting legs installed on the closed box, a control panel installed on the closed box, and a first gas pipeline installed on the closed box. The driving motor is installed at the lower end of the closed box, the installation sleeve is installed at the output end of the driving motor, the outer magnetic rotor is installed on the installation sleeve, the limiting frame is installed on the closed box, the containing table is rotationally connected to the limiting frame, and the inner magnetic rotor is installed on the containing table and transmits magnetic force with the outer magnetic rotor. The sample table is driven to rotate by the magnetic coupling driver, and a sample is dynamically and uniformly exposed in a thermal field and a reaction atmosphere in a testing process by combining an airflow field formed by the inclined spray head, so that the problem of non-uniform heating and reaction caused by a fixed position is fundamentally solved, and the accuracy and reliability of a testing result are greatly improved.

The invention provides a gaseous target for generating monoenergetic neutrons. The gaseous target comprises a sealing flange, an inlet window front window, an inlet window rear window, a blocking window and a vacuum system. Two inlet windows are arranged in the front and back, a front gas target chamber and a rear gas target chamber are constructed in a gaseous target, helium is filled into the target chamber composed of the front window and the rear window, deuterium or tritium gas is filled into the target chamber composed of the rear window and the stopping window, and the situation that radioactive gas escapes to pollute an accelerator pipeline due to damage of the inlet windows of the target chambers is effectively prevented through redundancy design. An inlet window of the gaseous target is made of Mo foil with the thickness smaller than 10 micrometers, a blocking window is made of Au foil with the thickness smaller than 150 micrometers, the energy width of the generated neutrons is smaller than 2%, and when the beam intensity is stable, the variation of the neutron fluence within 8 hours is smaller than 5%. The monoenergetic neutrons generated by the gaseous target are low in energy loss and excellent in monochromaticity, the design precision requirement of the fourth-generation nuclear reactor is met, and a guarantee is provided for commercialized popularization of the fourth-generation nuclear reactor.

The invention relates to a nuclear fusion power generation ship and method, the nuclear fusion power generation ship is used for sailing to a target sea area and supplying power to electric facilities, and the nuclear fusion power generation ship comprises a ship platform and a nuclear fusion power generation system arranged on the ship platform, the nuclear fusion power generation system comprises a nuclear fusion reaction unit used for realizing controlled fusion reaction of deuterium and tritium to generate continuous energy; the seawater circulating unit is connected with the nuclear fusion reaction unit and is used for extracting deuterium from seawater and supplementing fuel for the nuclear fusion reaction of the nuclear fusion reaction unit; and the energy conversion unit is connected with the nuclear fusion reaction unit and is used for converting energy generated by the nuclear fusion reaction unit into electric energy. Compared with the prior art, the invention aims to provide a stable, reliable and environment-friendly energy solution for the ocean area far away from the land through the integrated nuclear fusion technology, has the characteristics of cleanness, high efficiency, stability and sustainability, and can meet the energy demand of the area far away from the land.

The present disclosure provides a composition comprising a compound having the structure (A) wherein each of H1, H2, H3, H4, H5, H6, and H7 is independently hydrogen or a deuterium-enriched -H site; and wherein at least one of H1, H2, H3, H4, H5, H6, and H7 is a deuterium-enriched -H site, or a salt or ester thereof.