7 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.

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.

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.

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.