Patent classifications
G21F5/06
CHARGEABLE ATOMIC BATTERY AND ACTIVATION CHARGING PRODUCTION METHODS
A chargeable atomic battery (CAB) includes a plurality of CAB units and a CAB housing to hold the plurality of CAB units. Each of the CAB units are formed of a precursor compact including precursor material particles embedded inside an encapsulation material. The precursor material particles include a precursor kernel formed of a precursor material that is initially manufactured in a stable state and convertible into an activated material that is an activated state via atomic irradiation by a particle radiation source. Upon the precursor material being converted, the precursor material is in a partially depleted state such that an initial portion of the precursor material is depleted and a recharge portion of the precursor material is convertible into the activated state via atomic irradiation by the particle radiation source for recharging the chargeable atomic battery.
CHARGEABLE ATOMIC BATTERY AND ACTIVATION CHARGING PRODUCTION METHODS
A chargeable atomic battery (CAB) includes a plurality of CAB units and a CAB housing to hold the plurality of CAB units. Each of the CAB units are formed of a precursor compact including precursor material particles embedded inside an encapsulation material. The precursor material particles include a precursor kernel formed of a precursor material that is initially manufactured in a stable state and convertible into an activated material that is an activated state via atomic irradiation by a particle radiation source. Upon the precursor material being converted, the precursor material is in a partially depleted state such that an initial portion of the precursor material is depleted and a recharge portion of the precursor material is convertible into the activated state via atomic irradiation by the particle radiation source for recharging the chargeable atomic battery.
CONTAINER FOR STORING AND/OR TRANSPORTING SPENT NUCLEAR FUEL
A container for storing and/or transporting spent nuclear fuel. The container includes a body that defines an internal cavity that holds the spent nuclear fuel and an outer surface. The outer surface has holes formed therein into which trunnions are positioned. The container can be lifted by a lift yoke by coupling the lift yoke to the trunnions. The trunnions may include first and second components such that the first component is slidable in its axial direction relative to the second component when a force that exceeds a threshold acts on the second component. Thus, the second component may be slidable between a protruded state in which a portion of the second component protrudes from the outer surface of the body and a retracted state in which the second component does not protrude from the outer surface of the body.
CONTAINER FOR STORING AND/OR TRANSPORTING SPENT NUCLEAR FUEL
A container for storing and/or transporting spent nuclear fuel. The container includes a body that defines an internal cavity that holds the spent nuclear fuel and an outer surface. The outer surface has holes formed therein into which trunnions are positioned. The container can be lifted by a lift yoke by coupling the lift yoke to the trunnions. The trunnions may include first and second components such that the first component is slidable in its axial direction relative to the second component when a force that exceeds a threshold acts on the second component. Thus, the second component may be slidable between a protruded state in which a portion of the second component protrudes from the outer surface of the body and a retracted state in which the second component does not protrude from the outer surface of the body.
STORAGE SYSTEM FOR RADIOACTIVE NUCLEAR WASTE WITH PRESSURE SURGE PROTECTION
A radioactive nuclear waste storage system includes a cask comprising a hermetically sealed internal cavity configured for holding the waste such as spent nuclear fuel submerged in an inventory of water. One or more pressure surge capacitors disposed inside the cask include a vacuum cavity evacuated to sub-atmospheric conditions prior to storage of fuel in the cask. At least one rupture disk seals a vacuum chamber inside each capacitor. Each rupture disk is designed and constructed to burst at a predetermined burst pressure level occurring inside the cask external to the capacitor. This allows excess cask pressure occurring during a high pressure excursion resulting from abnormal operating conditions to bleed into capacitor, thereby returning the pressure inside the cask to acceptable levels. In one embodiment, the capacitors are located in peripheral regions of the cask cavity adjacent to the circumferential wall of the cask body.
Transfer cask for spent nuclear fuel
The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.
Devices and systems for material transportation
Various embodiments relate to devices for transporting high-assay low-enriched uranium (HALEU). A device may include at least one section, wherein each section of the at least one section includes a number of storage tubes. Each storage tube, which is configured to receive and hold a container, extends from adjacent a first end of the section toward a second, opposite end of the section. Each section further includes a number of flux traps, wherein each storage tube of the number of storage tubes is at least partially surrounded by a flux trap of the number of flux traps Associated systems are also disclosed.
STORING HAZARDOUS WASTE MATERIAL
A nuclear waste storage system includes a human-unoccupiable directional drillhole formed from a terranean surface into a subterranean formation, the drillhole including a substantially vertical portion and a substantially horizontal portion that includes a hazardous waste repository for nuclear waste storage; a casing including one or more tubular sections sized to fit within the drillhole; and a coating attached to an exterior surface of the casing, the exterior surface facing a rock formation through which the drillhole is formed.
Small modular mobile fission reactor
A mobile modular reactor, in particular, a graphite-moderated fission reactor, has an active core region and at least a portion of control region(s) that are located within an interior volume of a pressure vessel. Flow annulus features located in the flow annulus between an outer surface of the control rod/fuel rod and an inner surface of the cladding of the channel in which the rod is located stabilizes the flow annulus and maintains a reliable concentricity between the inner and outer claddings that envelope the flow annulus. Flow annulus features are equally circumferentially spaced at longitudinally separated locations and the flow annulus features at successive, longitudinally separated locations are rotationally offset relative to each other. For purposes of transportability, the pressure vessel is sized for mobile transport using a ship, train or truck, for example, by fitting within a shipping container.
Small modular mobile fission reactor
A mobile modular reactor, in particular, a graphite-moderated fission reactor, has an active core region and at least a portion of control region(s) that are located within an interior volume of a pressure vessel. Flow annulus features located in the flow annulus between an outer surface of the control rod/fuel rod and an inner surface of the cladding of the channel in which the rod is located stabilizes the flow annulus and maintains a reliable concentricity between the inner and outer claddings that envelope the flow annulus. Flow annulus features are equally circumferentially spaced at longitudinally separated locations and the flow annulus features at successive, longitudinally separated locations are rotationally offset relative to each other. For purposes of transportability, the pressure vessel is sized for mobile transport using a ship, train or truck, for example, by fitting within a shipping container.