13 results about "Enriched uranium" patented technology

The invention discloses a parameter calculation method and device for enriched uranium, equipment, a medium and a product. The method comprises the steps that a first parameter input operation is received, the first parameter input operation is an operation triggered when a user inputs a first enriched uranium parameter in a first parameter input window, and the first enriched uranium parameter comprises the number of enriched uranium and enriched uranium abundance; displaying the first enriched uranium parameter; receiving a parameter calculation operation, wherein the parameter calculation operation is a triggering operation of a user on a parameter calculation button; in response to the parameter calculation operation, performing parameter calculation based on the first enriched uranium parameter in combination with a pre-generated parameter calculation model; and displaying a parameter calculation result, so that the problem that the manual parameter calculation result is inaccurate is solved, automatic parameter calculation is realized, a user can complete calculation only by inputting the first enriched uranium parameter without manual calculation, the calculation result is more accurate, human interference factors do not exist, the workload of the user is reduced, and the user experience is improved. And the calculation speed is improved.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

Thorium-based fuel bundles are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300 / 600 / 900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt%. Reprocessing of spent fuel bundles is also avoided.

Passive reactivity control technologies that enable reactivity control of a nuclear thermal propulsion (NTP) system with little to no active mechanical movement of circumferential control drums. By minimizing or eliminating the need for mechanical movement of the circumferential control drums during an NTP burn, the reactivity control technologies simplify controlling an NTP reactor and increase the overall performance of the NTP system. The reactivity control technologies mitigate and counteract the effects of xenon, the dominant fission product contributing to reactivity transients. Examples of reactivity control technologies include, employing burnable neutron poisons, tuning hydrogen pressure, adjusting wait time between burn cycles or merging burn cycles, and enhancement of temperature feedback mechanisms. The reactivity control technologies are applicable to low-enriched uranium NTP systems, including graphite composite fueled and tungsten ceramic and metal matrix (CERMET), or any moderated NTP system, such as highly-enriched uranium graphite composite NTP systems.

The invention relates to hydrometallurgy. A method of concentrating uranium in a uranium-containing solution includes separating the uranium-containing solution by nanofiltration, and concentrating uranium in a concentrate. The used uranium-containing solution is uranium-rich eluent. The uranium-containing solution is first fed into a fine filter to remove suspended particles before separation by nanofiltration. And the solution is separated by using a membrane assembly in the third-stage or fourth-stage nano-filtration. The membrane module is a module having a selective membrane. A portion of the concentrate obtained after the last nanofiltration membrane module is sent back to the starting point of the nanofiltration process. As a result, the efficiency of enriching uranium from the initial uranium-containing solution is improved.

Thorium-based fuel bundles according to one or more embodiments of the present invention are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300 / 600 / 900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to, according to one or more embodiments, 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt %. Reprocessing of spent fuel bundles is also avoided.

The invention provides a neptunium-uranium mixed target for producing plutonium 238 through irradiation of a heavy water reactor. The neptunium-uranium mixed target comprises at least one fuel rod, the fuel rod comprises at least one fuel rod; the fuel rod comprises a first pellet, the first pellet comprises neptun-237 and enriched uranium, and R * mU1 = 0.72% * (mU1 + mNp) is met, mU1 represents the mass of the enriched uranium in the first pellet, and mNp represents the mass of the enriched uranium in the first pellet. MNp represents the mass of the neptun-237 in the first pellet; r represents the content of uranium-235 in the enriched uranium.

A fuel assembly used for CANDU reactor fission method MO-99 production comprises composite fuel rods located at symmetrical positions in a center, a first circle and a second circle and conventional fuel rods serving as outer ring fuel rods. The composite fuel rod sequentially comprises a metal zirconium rod located in the center, an annular low-enriched uranium target layer arranged on the outer side of the metal zirconium rod in a sleeving mode and a zirconium alloy cladding covering the outer side of the low-enriched uranium target layer from inside to outside in the radial direction. Certain fuel rods of one assembly are replaced with metal zirconium rods (namely composite fuel rods) with low-enriched uranium cladding layers to achieve Mo-99 fission method production, meanwhile, heat release of fission target pieces can be used for making up for insufficient assembly power caused by replacement of the fuel rods, and inherent cooling agents in pressure pipes can also effectively cool the target pieces. And the safety production of the reactor is ensured.

The present invention provides thorium-based fuels for pressurized heavy water reactors (e.g., fuel pellets, fuel pins, and / or fuel bundles), as well as methods for manufacturing and using the same. [Solution] The fuel composition of the bundle consists of 60 wt% or more thorium, with the remaining fuel being low-enriched uranium (LEU) of 235U with an enrichment level of 13-19.95%. The use of such a thorium-based fuel bundle provides a non-brederate spent fuel bundle having (1) 100% of the nominal power throughout the entire lifecycle of the core, (2) high burnup, and (3) a total isotope uranium concentration of less than 12 wt%. Reprocessing of spent fuel can also be avoided.

The present invention relates to an AlN-based space deep ultraviolet laser based on nuclear pumping, which includes a working substance, an excitation energy source and an optical resonant cavity, wherein the working substance includes an AlN semiconductor medium capable of realizing energy level transition; the excitation energy source uses nuclear energy to directly pump the working substance to give energy to the atoms of the working substance to excite; the optical resonant cavity allows the working substance to continuously undergo stimulated radiation, while limiting the output direction of the laser; the diamond polycrystalline layer, as a heat dissipation material with high thermal conductivity, can also be used as a moderator for nuclear fuel; the diamond polycrystalline layer is sequentially stacked with an AlN-based semiconductor active region, highly enriched uranium and an AlN-based semiconductor active region to form a core-laser medium stacking unit structure, thereby forming a reactor. The present invention utilizes nuclear energy to directly pump AlN-based semiconductor materials to realize a deep ultraviolet laser with a lasing wave of 150nm-260nm, with an output power above the MW level, and at the same time, has a small size, a compact structure and good maneuverability.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

The automatic feeding system of uranium chemical enriched materials includes a base, a barrel turning device and a feeding and unloading device; a track is fixed on the base; the barrel turning device includes a bracket, a hanger, a turning drive mechanism and a barrel locking mechanism; the turning drive mechanism is associated with the hanger to drive the hanger to turn along a vertical plane; the feeding and unloading device includes a moving trolley A, a first shifting control mechanism, a barrel bearing frame and a second shifting control mechanism; the moving trolley A is movably installed on the track; the first shifting control mechanism controls the moving trolley A to move on the track, and then dock or avoid the hanger; the second shifting control mechanism controls the barrel bearing frame to move between the moving trolley A and the barrel locking area. The present invention can realize the automatic feeding operation of radioactive uranium chemical enriched materials, and the feeding process has high stability, reliability and automation, and the feeding effect is clean and thorough.

A method for producing a fuel kernel is provided. The method comprises producing a dry fissile material comprising enriched uranium, forming a particle from the dry fissile material, the particle having a diameter of 1 millimeter or less; and thermally processing the particle to produce the fuel kernel. A press system for dry fissile material is also provided.