19 results about "Deuterium ions" patented technology

This invention discloses a conveniently detachable, actively water-cooled solid-state deuterium target based on a compact neutron source, comprising a micron-sized solid titanium film, a titanium film carrier, and a water-cooled substrate. Deuterium is deposited in the solid titanium film by bombarding it with a deuterium ion beam, and neutrons are generated by collisions with the subsequent deuterium ion beam. Oxygen-free copper, with its high thermal conductivity, is used as the carrier for the titanium film. The threaded structure on the side of the titanium film carrier allows for convenient installation and removal from the water-cooled substrate. The oxygen-free copper substrate, with multiple annular water-cooling structures inside, enables rapid and effective removal of heat flux from the target, preventing deuterium particles deposited in the solid titanium film from desorbing due to excessive temperature, thus avoiding impact on neutron yield. This invention provides a conveniently detachable, actively water-cooled solid-state deuterium target suitable for compact deuterium-deuterium neutron generators, providing a sound technical foundation for the widespread application of compact accelerator neutron source systems in production and daily life.

A rotating target high yield compact D-D neutron generator disclosed by the present invention comprises an ion source unit, a vacuum main body unit and a target unit, the ion source unit generates a deuterium ion beam, the deuterium ion beam is introduced into a vacuum chamber and passes through a leading-out accelerating electrode for acceleration, and the accelerated deuterium ion beam bombards the circumferential target surface of a molybdenum target to generate a deuterium ion beam. And deuterium-deuterium fusion reaction with deuterium nuclei injected into the molybdenum target in advance is carried out, fast neutrons are released, and the neutron yield is improved. The rotating driver of the target unit drives the molybdenum target of the cylindrical structure to rotate through the insulating rotating shaft, the molybdenum target rotates to distribute beam power to the circumferential target surface of the molybdenum target, a cooling medium is conveyed to one side of the inner side wall of the molybdenum target in combination with the cooling channel, the molybdenum target is cooled, and the service life of the target unit can be effectively prolonged. The leading-out accelerating electrode is located in the vacuum cavity, operation of the vacuum main body unit is not affected by external humidity and temperature environment conditions, high-voltage ignition discharge can be effectively restrained, and the safety performance of a high-voltage electric field is improved.

The invention relates to the technical field of engineering logging, and discloses a low-power-consumption radio frequency ion source logging neutron tube and a working method, deuterium gas is ionized into deuterium ions through an ion source, the deuterium ions are accelerated under the action of a strong electric field to obtain energy, and the high-energy deuterium ions bombard a deuterium / tritium target to generate nuclear reaction to generate neutrons. The power requirement of the radio frequency source can be greatly reduced. Compared with an inductive coupling type radio frequency ion source neutron tube, the capacitive coupling type neutron tube has the advantages that D1 + 1 in plasma is increased to 50%, the required power is 25%-30% of that of the inductive coupling type neutron tube, the load of a neutron generator is greatly reduced, the D-D deuterium neutron tube is further applied to engineering practice, and powerful technical support is provided for green and environment-friendly well logging.

The invention discloses a laser neutron yield increasing method based on a composite conversion target, which comprises the following steps of: arranging a plurality of elements to form the composite conversion target, bombarding the composite conversion target by using a deuterium ion beam obtained by interaction of laser and a heavy water liquid film target, and realizing neutron yield increasing through nuclear reaction section optimization; elements in the composite conversion target comprise at least two of T, D, < 7 > Li and < 9 > Be. According to the laser neutron yield increasing method based on the composite conversion target, the neutron yield and the average flux of a repetition frequency laser neutron source method are greatly increased, and the problem of instability in the continuous production process of a heavy water liquid film target is solved.

This application discloses a fusion reactor ash gas treatment device, belonging to the field of fusion reactor technology. The fusion reactor ash gas treatment device includes: a shell forming a vacuum chamber; a gas supply unit for inputting ash gas into the vacuum chamber; an inductively coupled plasma generator for generating plasma from the ash gas input into the vacuum chamber; a hydrogen selective membrane disposed within the vacuum chamber, dividing the vacuum chamber into a first chamber and a second chamber; the inductively coupled plasma generator is at least partially located in the first chamber; deuterium ions and tritium ions pass through the hydrogen selective membrane into the second chamber and combine to form deuterium-tritium gas; a bias power supply electrically connected to the hydrogen selective membrane for applying a negative bias voltage; a first discharge section connected to the first chamber; and a second discharge section connected to the second chamber. This device achieves rapid treatment and recycling of the ash gas, is not only compact and easy to operate, but also reduces the amount of deuterium-tritium gas retained and energy consumption, improving operational reliability.

A method for producing a neutrons includes triggering a raising or a lowering of a temperature of a pyroelectric crystal of less than about 40° C. to produce a voltage of negative polarity of at least −100 keV on a surface of a deuterated or tritiated target coupled thereto. A deuterium ion source is pulsed to produce a deuterium ion beam. The accelerating of the deuterium ion beam is achieved by accelerating voltage of the pyroelectric crystal toward the deuterated or tritiated target to produce neutrons. Furthermore, the pyroelectric crystal, the deuterated or tritiated target, and the deuterium ion source are coupled to a common support. The method also includes throwing the common support housing the pyroelectric crystal, the deuterated or tritiated target, and the deuterium ion source near an unknown threat for identification thereof.

The invention discloses a fusion reactor discharged ash gas treatment device, and belongs to the technical field of fusion reactors. The fusion reactor discharged ash gas treatment device comprises a shell forming a vacuum chamber; the gas supply part is used for inputting ash discharge gas into the vacuum chamber; the inductively coupled plasma generating device is used for enabling the discharged ash gas input into the vacuum chamber to generate plasma; the hydrogen selective membrane is arranged in the vacuum chamber and divides the vacuum chamber into a first cavity and a second cavity, the inductively coupled plasma generating device is at least partially located in the first cavity, and deuterium ions and tritium ions enter the second cavity through the hydrogen selective membrane and are combined to form deuterium and tritium gas; the bias power supply is electrically connected with the hydrogen selection membrane and is used for applying bias voltage with negative potential; the first discharge part is communicated with the first cavity; and the second discharge part is communicated with the second cavity. The deuterium and tritium gas treatment device not only is compact in structure and simple and convenient to operate, but also can reduce the retention volume and energy consumption of deuterium and tritium gas, and improves the operation reliability.

To obtain deuterium in a gas state from a mixed gas of hydrogen and deuterium at a low cost.A first electrode 11 is an electrode made of a metal allowing hydrogen (H component and D component) to permeate therethrough (hydrogen permeable metal), and the hydrogen permeable metal is Pd, for example. H ions and D ions having permeated through the first electrode 11 flow to the side of a second electrode 12 in a proton conduction layer 20. When the first electrode 11 is used as an anode and the second electrode 12 as a cathode, H ions and D ions flow in the proton conduction layer 20 from the left to the right in the drawing. In that case, hydrogen component in an input gas is more likely to flow into an atmosphere on the cathode side than deuterium component, and an H / D composition ratio accordingly becomes higher in a product gas than in the input gas. In an exhaust gas extracted after H and D components in the input gas are thus consumed, D component has been enriched.

The present application discloses a compact neutron generator based on an all-glass helicon wave ion source, which belongs to the field of accelerator neutron sources. The neutron generator includes a helicon wave ion source part, a cavity part, and a target part. First, deuterium gas is introduced into the ion source chamber. Then, the deuterium gas is excited by an antenna, thereby generating a helicon wave plasma. Under the constraint of a magnetic field, deuterium ions are first extracted in the form of a beam by the potential difference between an extraction electrode and an ion source cover plate, and then accelerated by the electric field between the extraction electrode and a titanium target. Finally, the deuterium ion beam bombards the titanium target, and a deuterium-deuterium fusion reaction occurs to generate neutrons. At the same time, an arc magnet and a resistor are used to suppress the secondary electrons generated by the target, so as to prevent the secondary electrons from being reversely accelerated and entering the ion source chamber. The present application has the advantages of low energy consumption, a compact structure, high plasma density, autonomous cooling, a good secondary electron suppression effect, high extraction beam intensity, and a high neutron yield.

The invention discloses a deuterium-titanium target based on a compact accelerator neutron source, which belongs to the technical field of neutron generators and comprises a micron-sized solid titanium film prepared by magnetron sputtering coating, a titanium film carrier and a water-cooling substrate. According to the invention, oxygen-free copper with strong heat transfer capability is adopted as a carrier of the titanium film, and a double-thread structure in the water-cooling substrate is utilized, so that the heat of the deuterium ion beam is quickly and efficiently removed, and deuterium particles deposited in the solid titanium film are prevented from being desorbed from the titanium film due to too high temperature to influence the performance of the neutron generator. According to the compact type accelerator neutron source, the maximum heat flux density can reach 3.5 MW / m < 2 >, and theoretically, when the beam power of the compact type accelerator neutron source reaches 2600 W, the requirement for heat load removal can still be met. The invention provides the double-thread deuterium-titanium target suitable for the compact deuterium-deuterium neutron generator, the thermal load removal capability of the removal target is greatly improved, and technical support is provided for stable operation of a compact accelerator neutron source system.

The invention provides a neutron tube performance optimization method. The method comprises the following steps: determining a first distribution range of extraction configuration information of a deuterium ion extraction structure; based on the first distribution range and a preset ion source extraction electrode structure model, simulating and calculating optimal extraction performance information of the deuterium ions; setting extraction configuration information corresponding to the optimal extraction expression information as target configuration information of the deuterium ion extraction structure; determining a second distribution range of target configuration information of the target structure; based on the second distribution range and a preset neutron tube target model, simulating and calculating the optimal heat dissipation associated information of the target when the deuterium ion extraction structure applies the target configuration information; and setting the target configuration information corresponding to the optimal heat dissipation associated information as the target configuration information of the target. According to the technical scheme, the deuterium ion extraction structure and the target heat dissipation structure are synergistically optimized, and the performance of the neutron tube is remarkably improved.

The present disclosure provides a D−7Li neutron generator system and methods for producing a large amount of 225Ac. High flux 10 and 13 MeV neutrons generated by the (D−7Li) reaction are used to irradiate 226Ra forming 225Ra / 225Ac via the 226Ra(n,2n)225Ra reaction. The generator consists of three main components: (1) a surface-production type negative ion source; (2) an extraction and acceleration column; and (3) a beam target Lithium electrode to irradiate 226Ra resulting in the formation of 225Ac. The methods enable the negative deuterium ion-base compact neutron generation system to generate reliably high yield of neutron flux in the absence of back-streaming electrons for producing 225Ac in large quantities but with a very small percentage of 227Ac (˜1%).

The invention provides a multi-energy multi-ion linear accelerator for isotope production. The multi-energy multi-ion linear accelerator comprises an ion source system located on a main path of a beam, a radio frequency quadrupole accelerator and a multi-section drift tube linear acceleration unit, the ion source system comprises a plurality of ion sources, deflection magnets are arranged between two adjacent sections of the drift tube linear acceleration unit and on the downstream of the last section, and the deflection magnets can be switched between an opening state and a closing state and are used for enabling beam current to deflect to a sub-path of the beam current in the opening state and enabling the beam current to deflect to a sub-path of the beam current in the closing state. Therefore, each deflection magnet serves as a beam extraction position when being opened, and extraction of beams with different energies is realized. The multi-energy multi-ion linear accelerator for isotope production can output ion beams with different energies through different beam extraction positions, and accelerated ions can be protons, deuterium ions, helium ions, carbon ions, nitrogen ions, oxygen ions and other ions. Therefore, isotope production types are enriched, and isotope production efficiency is improved.

The invention discloses a radio frequency ion source for controllable source logging and a working method, and the method comprises the steps: one end of a high-voltage feed needle is disposed in a tube shell, and an inductance coil is wound on the tube shell; the permanent magnet rings are positioned on two sides of the inductance coil; the extraction electrode is positioned at the other end of the tube shell; the high-voltage feed needle is externally connected with a high-voltage power supply, and the high-voltage power supply feeds high voltage into the plasma through the high-voltage feed needle; the inductance coil is externally connected with a radio frequency power source and an impedance matching circuit; the radio frequency power source is connected with the inductance coil through the impedance matching circuit to form an induction electromagnetic field, so that the working gas in the tube shell is ionized, and then plasma is formed. According to the invention, energy is fed in through transmission coupling of the high-voltage feed needle and a radio frequency signal, so that the discharge chamber can obtain stable high-component monatomic deuterium ion plasma under high vacuum; according to the invention, the monatomic ion component of the ion source is greatly improved, and the working stability and the working life of the logging neutron tube using the radio frequency ion source are further improved.

A compact neutron generator based on an all-glass helicon ion source. The compact neutron generator comprises a helicon ion source part (1), a chamber part (2) and a target part (3). First, deuterium gas is introduced into an ion source chamber (106), and the deuterium gas is then excited by means of an antenna (107), so as to generate helicon plasma; under magnetic field confinement, ions are first extracted as a beam by means of the potential difference between an extraction electrode and an ion source cover plate (109), and are then accelerated by an electric field between the extraction electrode and a titanium target (306); and finally, the deuterium ion beam bombards the titanium target (306), such that neutrons are produced by means of a deuterium-deuterium fusion reaction. In addition, an arc-shaped magnet (303) and a resistor (307) are also used to suppress secondary electrons, which are produced during target bombardment, thereby preventing the secondary electrons from being accelerated backward into the ion source chamber (106).

This invention relates to an inertial electrostatic confinement fusion device with electron injection neutralization, comprising a cathode sphere, an anode, a cathode high-voltage introduction support rod, a high-energy electron injection gun, a vacuum system, and a high-voltage power supply system. The high-energy electron injection gun and the electron injection gun within the sphere inject neutralizing electrons into the sphere and between the sphere and the anode of the inertial electrostatic confinement fusion device, thereby reducing or eliminating the space charge force generated by deuterium ions, increasing the deuterium ion density within the sphere, and thus improving neutron yield and break-even ratio.

The application relates to a method for analyzing the interaction dynamics of double-beam counter-propagation laser and ultrathin target. The method comprises the following steps: based on the constructed physical model of the interaction between double-beam counter-propagation relativistic laser and ultrathin target, the particle simulation method is used to analyze the compression condition and the maximum deuterium ion density information of the ultrathin target under one-dimensional and two-dimensional conditions by changing the initial relative phase difference and the circularly polarized laser electric field vector rotation direction of the two beams, the ion acceleration effect information generated by the interaction between the counter-propagation laser and the ultrathin target under different parameters is obtained, and the optimal ion acceleration scheme is determined. The interaction between the two-beam counter-propagation relativistic laser and the ultrathin target is realized, the polarization direction and the rotation direction of the two lasers are calibrated, the calibration relationship between the ion acceleration and the laser parameters is displayed, and the method can provide a reference for the dynamic research of the double-beam counter-propagation laser and the ultrathin target.

It is proposed a method and device for the realization and reaching the required parameters for a nuclear reaction of light nucleus in liquid. The time for the plasma sustainability is achieved by excitation of long train of high peak intensity ps pulses. The preliminary estimations show a power intensity of 1019 - 1020 W / cm2 ( corresponding for the wavelength of 1064nm is round 5.1011 V / m electric field ). It is observed, that the emission of the D ions at 656nm continues after the end of the excitation and ions recombination life time, which leads to the conclusion that a high energy exothermal reaction is triggered.

The invention relates to the technical field of short-pulse laser-driven neutron sources, in particular to a method for improving the yield of a short-pulse laser-driven neutron source. The invention provides a method for improving the yield of a short-pulse laser-driven neutron source, which comprises the following steps: bombarding the front surface of a target material by main laser within 10 minutes after bombarding the back surface of the target material by cleaning laser, so that the back surface of the target material generates a sheath electric field, and accelerating to obtain deuterium ions and protons; the vertical projection point of the light spot range of the main laser bombarded to the surface of the target material on the back surface of the target material falls within the light spot range of the cleaning laser bombarded to the surface of the target material, and the target material is a deuterium-containing planar target material; the deuterium ions and the protons bombard the LiF target material to generate nuclear reaction, and neutrons are obtained. According to the method, the deuterium ion acceleration can be greatly enhanced, and the neutron yield is greatly improved.