5 results about "Deuterium" patented technology

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.

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 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.