35 results about "Fusion neutron" patented technology

A laser inertial-confinement fusion-fission energy power plant is described. The fusion-fission hybrid system uses inertial confinement fusion to produce neutrons from a fusion reaction of deuterium and tritium. The fusion neutrons drive a sub-critical blanket of fissile or fertile fuel. A coolant circulated through the fuel extracts heat from the fuel that is used to generate electricity. The inertial confinement fusion reaction can be implemented using central hot spot or fast ignition fusion, and direct or indirect drive. The fusion neutrons result in ultra-deep burn-up of the fuel in the fission blanket, thus enabling the burning of nuclear waste. Fuels include depleted uranium, natural uranium, enriched uranium, spent nuclear fuel, thorium, and weapons grade plutonium. LIFE engines can meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the highly undesirable stockpiles of depleted uranium, spent nuclear fuel and excess weapons materials.

The invention discloses a high-pressure-difference gas target device suitable for a superhigh-intensity deuterium tritium fusion neutron source. The high-pressure-difference gas target device comprises an accelerator interface and a reaction gas cavity. The device also comprises a vacuum difference system, a beam constraint device and a reaction gas cycle collection device, wherein the vacuum difference system comprises a second-stage difference chamber, a first-stage difference chamber, a small-bore long pipeline and a small-bore flange; the beam constraint device is used for carrying out focusing on a deuterium beam in the small-bore long pipeline to enable beam envelope to be smaller than the inner diameter of the small-bore long pipeline and the small-bore flange; and the reaction gas cycle collection device is connected with the first-stage difference chamber and the second-stage difference chamber through a vacuum pump and is used for carrying out separation and purification on the gas discharged by the vacuum pump and then, enabling the gas to enter the reaction gas cavity through a throttle valve. The deuterium beam output from the accelerator interface passes through the vacuum difference system and realizes pressure jump from 10<-5>Pa at the tail end of the accelerator to 10<-3>Pa of the reaction gas cavity, and then, has fusion reaction with a tritium gas or a deuterium gas in the reaction gas cavity to generate high-energy fusion neutrons, and the tritium gas or the deuterium gas is subjected to online purification, collection and recycling.

The invention discloses a multi-type neutron energy spectrum regulation and control target apparatus. The apparatus comprises a coupled target reaction apparatus and a target replacing apparatus in aneutron energy spectrum regulation and control apparatus. The apparatus is applied to a fusion neutron source driven sub-critical mixed pile energy system; deuterium beam generated by a strong flow deuterium tritium fusion neutron generator bombards a solid-state target to generate a high-flux deuterium tritium fusion neutron beam; then the fusion neutron bombards a sub-critical coating layer witha neutron multiplication material; through neutron multiplication and energy spectrum optimization, neutron energy spectrum regulation and control is realized; the coupled target reaction apparatus comprises a vacuum tube, a target tube and a target sheet assembly positioned in the target tube; and the target replacing apparatus comprises a target replacing cavity, a target sheet storage cavity,a target sheet replacing apparatus, and a target sheet conveying apparatus for conveying the target sheet assembly to the target pipe. Labor intensity of the working staff in target replacing is lowered effectively, meanwhile, the target replacing efficiency is improved, and operational stability of a clean energy system is improved.

A method and system for achieving fusion is provided. The method includes providing laser source that generates a laser beam and a target that includes a capsule embedded in the target and filled with DT gas. The laser beam is directed at the target. The laser beam helps create an electron beam within the target. The electron beam heats the capsule, the DT gas, and the area surrounding the capsule. At a certain point equilibrium is reached. At the equilibrium point, the capsule implodes and generates enough pressure on the DT gas to ignite the DT gas and fuse the DT gas nuclei.

Fusion devices produce the fusion of neutral atoms and ions in the absence of neutrons in "neutronless fusion" because the products utilize strong ion-neutral coupling at high neutral density. Ions and neutrals rotate together in a cylindrical chamber due to frequent collisions. The high magnetic force makes it possible to reach high rotational energies; the magnetic field in the medium can be set at very high values ​​due to the absence of magnetic charges. Repeated acceleration by strong magnetic forces in the azimuthal direction makes it possible to obtain very high ion velocities. Fusion mainly occurs between neutral particles. This method can also be applied to fusion with neutrons. Conventional fusion schemes and neutron sources can use the principles described above to produce high-energy, high-density neutral particles.

The invention discloses a lead-based neutron multiplier suitable for a fusion reactor solid cladding, which adopts a composite sphere design of a three-layer core-shell structure: a PbxMy sphere core material is a lead-based intermetallic compound with high melting point and excellent neutron multiplication performance, including but not limited to LaPb3, CePb3, Zr5Pb4, Zr5Pb3, PrPb3, NbPb3, Nd5Pb4, Nd5Pb3 and PbS, and plays a role in neutron multiplication; the middle shell layer is a PbxMy-Li2O metal ceramic composite material, the comprehensive tritium breeding ratio of the cladding is improved through efficient tritium production of Li2O and fusion neutrons, meanwhile, the metal ceramic composite material and a PbxMy metal interface have good thermodynamic matching, and the overall core-shell structure is stable; and the PbxMy shell layer is a thin film, so that the overall chemical inertness of the spherical shell is ensured. The invention provides a neutron multiplier design which is good in economical efficiency and can meet the fusion reactor tritium breeding requirement, and a feasible solution can be provided for replacing pure beryllium.

The invention discloses a proton conductor ceramic membrane-based self-loop tritium target system which is mainly suitable for a deuterium and tritium fusion neutron generator. In the proton conductor ceramic membrane-based self-loop tritium target system, a proton conductor ceramic membrane is used as a core part of a tritium target, and the proton conductor ceramic membrane consists of a compact oxide ceramic solid electrolyte and two porous electrodes. A self-loop process comprises the following steps: tritiated water is ionized into tritium ions on an anode via an external power source, and the tritium ions are reduced into tritium atoms and subjected to deuterium and tritium fusion due to bombardment of a deuterium beam after spreading in the porous anodes and migrating to a cathode. Tritium which does not participate in a fusion reaction are oxidized into the tritiated water via a purifying system, and the tritiated water is recycled back to the anode and reused after being collected. Via the proton conductor ceramic membrane-based self-loop tritium target system, operating temperature of the tritium target can be improved to 800 DEG C and 1000 DEG C, cyclic utilization of tritium is realized, and a utilization rate of tritium can be greatly increased.

The invention relates to a small laser deuterium-deuterium fusion neutron tube with a high temperature and high pressure. An insulation layer is arranged in the inner wall of the tube. A cathode and an anode in the cathode are arranged in the tube. A cathode corner connected with the cathode and an anode corner connected with the anode are arranged on the external lower part of the tube. The top of the tube is a transparent body and the tube is filled with deuterium gas. In the invention, the external diameter of the cathode is 40 mm and the internal diameter is 30-34 mm, as well as the height is 110-150 mm. a center hole with an aperture of 20-23 mm is arranged on the bottom center of the cathode. The anode is positioned in the center hole of the bottom. The anode and the cathode have a same shaft. The diameter of the anode is 8-15 mm and the height is 100-120 mm. The tube is filled with deuterium gap. The neutron tube of the invention has the advantages of small volume, high temperature resistance, high pressure resistance, high productivity and long service life, etc. The neutron tube is a component of an oil logging tool which can satisfy the neutron-neutron well detection under the conditions of high temperature 150 DEG C or more than 150 DEG C and the high pressure 80MPa or more than 80MPa.

The invention discloses a laser fusion neutron irradiation effect test device, which includes a collection module, the collection module is equipped with a first pipeline and a second pipeline extending outward, wherein the remote end of the second pipeline is connected with a sample for placement assembly, used to fix the sample, the far end of the first pipeline is connected with a detection head assembly, used to measure the neutron dose near the sample, the collection module is connected to the detection head assembly through a first optical fiber, and the collection module is connected to the detection head assembly The sample placement components are connected by a second optical fiber, and the first optical fiber and the second optical fiber are placed in the first pipeline and the second pipeline respectively. The beneficial effect of the invention is that it can prevent corresponding parts in the collection module from being irradiated by neutrons, so as to ensure the accuracy of neutron dose measurement and effect evaluation.

The invention discloses a method and a system for producing a <252>Cf neutron source by a fusion-driven sub-critical system, the external neutron source is: D-T fusion neutron source; a fuel cycle mode is a U-Pu cycle mode, and the fusion-driven sub-critical system of the U-Pu cycle mode has higher neutron flux. The structure of a cladding layer is as follows: an actinide nuclide treatment area, a target area, a fissile fuel proliferation area or the fissile fuel proliferation area, a fission product treatment area and a reflection and shielding area are sequentially surrounded at the outside of a generation area of the external neutron source, and the various areas are separated by using structural materials. The target area adopts helium as a cooling agent, reaction substances of the target area are formed by stacking in small sphere shape, and the volume of total solids accounts for 60 percent to 90 percent of the total volume. A target ball is taken out after materials of the target area are continuously radiated for about one year in the fusion-driven sub-critical system; the <252>Cf has short half-life and can not be radiated for a long time.

The invention relates to a high thermal power target system suitable for deuterium and tritium fusion neutron sources. The system includes a deuterium beam, a beam scanning drive device, a target slice, a target slice drive device, a cooling structure, a cooling medium, a cooling medium circulation system, a beam transmission chamber, a cooling medium dynamic sealing structure, and a vacuum dynamic sealing structure. The beam scanning drive is used to drive the deuterium beam to move. The deuterium beam is located in the beam transmission chamber. The target slice drive device drives the target slice to move. The target slice is disposed on the moving path of the deuterium beam. The deuterium beam bombards a target spot formed by the target slice. The cooling structure is located in the target slice area where the target spot is located. The cooling medium is filled in the cooling structure. The cooling medium is circulated through the cooling medium circulation system. According to the invention, the tritium target system for the high intensity deuterium and tritium fusion neutron sources can maintain a target surface temperature of less than 200 DEG C when being subjected to bombardment with a deuterium beam of greater than 100 kw / cm2, the stable operation of the tritium target system is ensured, and then 14MeV high-energy fusion neutrons with neutron sources up to 1013 to 1015n / s are produced.

The invention discloses a fusion product comprehensive protection device for a Z-hoop condensation polymerization fission energy pile, and belongs to the field of nuclear reactor devices. The Z-hoop condensation polymerization fission energy pile is provided with a fusion target center and a first wall which is arranged on the periphery of the fusion target center and faces plasmas. The fusion product comprehensive protection device is characterized by comprising an inner gas atmosphere layer, a metal protection cover, an outer gas atmosphere layer and a first wall protection layer; the inner gas atmosphere layer, the metal protection cover, the outer gas atmosphere layer and the first wall protection layer are sequentially arranged from the fusion target center to the first wall facing the plasmas, the inner gas atmosphere layer is formed by inner layer protection gas, the fusion target center and the metal protection cover are filled with the inner layer protection gas, the outer gas atmosphere layer is formed by outer layer protection gas, the metal protection cover and the first wall protection layer are filled with the outer layer protection gas, and the first wall protection layer is arranged on the surface of the inner wall body of the first wall facing the plasmas. The fusion product comprehensive protection device is used for the Z-hoop condensation polymerization fission energy pile, fusion X rays, fusion ions and fusion debris can be absorbed and protected, fusion neutron transmission cannot be influenced, and meanwhile fusion reaction residual deuterium tritium fuel is easily recycled through the fusion product comprehensive protection device.

The invention discloses a method and a system scheme for constructing plasma capable of realizing a magnetic confinement fusion reaction by heating a mixture consisting of lithium, tritium and deuterium in a magnetic confinement device by utilizing neutrons. The neutrons required for heating the plasma are provided by performing doubling, moderating and reflecting on an external neutron source or fusion neutrons generated by a fusion reaction in a device through a cladding on the container wall of the magnetic confinement device. The lithium in the plasma is obtained by injecting lithium metal nano-particles or lithium deuteride projectiles. According to the method and the system scheme, the plasma is heated by MeV-level high-energy tritium particles and helium particles generated by a fission reaction caused by bombarding the lithium in the plasma by the neutrons. The plasma formed and maintained by the heating method is mainly deuterium lithium plasma. According to the heating method-based magnetic confinement fusion device, the problem about tritium self-sustaining is not required to be considered, the design of a fusion reactor is greatly simplified, and the economical efficiency of the fusion reactor is greatly improved.