Abstract: A nuclear fuel element for use in a nuclear reactor may include a plurality of metal fuel sheaths extending along a longitudinal fuel element axis and spaced apart from each other, the plurality of fuel sheaths comprising a first fuel sheath having an inner surface, an opposing outer surface and a hollow interior configured to receive nuclear fuel material. A carbon coating may be on the inner surface of the first fuel sheath. The carbon coating may include more than 99.0% wt of a carbon material including more than 20% wt of carbon nanotubes and less than about 0.01% wt of organic contaminants.

Abstract: A system for monitoring fissile material contents inside of a nuclear reactor can include at least a first neutron detector positioned outside a radiation shield and configured to detect a plurality of neutrons originating from the reactor core and having passed through the radiation shield, and configured to generate a first output signal, and a controller communicably linked to the first neutron detector to receive the first output signal and a power output of the nuclear reactor.

Abstract: In one aspect, a method of preconditioning stem cells comprising exposing stem cells to low dose radiation (LDR) is provided. In another aspect, a population of preconditioned stem cells is provided, wherein the population of 5 preconditioned stem cells is obtained by exposing stem cells to LDR. Uses of the preconditioned stem cells are also provided. In other aspects, the stem cells are muscle stem cells.

Abstract: A hydrogen storage assembly includes at least one wafer formed of a substrate material that produces metal hydride when exposed to a hydrogen-rich carrier fluid. The wafer can be supported by a housing and arranged so that the hydrogen-rich carrier fluid can flow over a reaction surface of the wafer. At least one heating element can be arranged to transfer heat to the wafer to attain an operating temperature suitable for hydrogen charging on the reaction surface. A de-activation material may be provided on the reaction surface for inhibiting formation of surface oxide that impedes hydrogen absorption during charging and hydrogen desorption during discharging. The at least one wafer can include a plurality of monolithic plate wafers spaced apart about a central axis of the assembly. The at least one wafer can include a plurality of monolithic disc wafers in at least one stacked arrangement.

Abstract: An article formed of a metal alloy is covered at least partially with a metal hydride and a shell metal to form an assembly. Load is applied to the assembly and the assembly is heated. The shell metal deforms around the article and the metal hydride and forms a gas proof seal. The metal hydride thermally decomposes to form hydrogen gas. At least a portion of the hydrogen gas dissociates and moves as monoatomic hydrogen into the article. The metal alloy can be a zirconium metal alloy, the metal hydride can be a zirconium metal hydride, and the shell metal can be substantially copper.

Abstract: The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.

Abstract: The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. There are restrictions on the allowable pressure drop across the strainer and the space available for installing this equipment. The finned strainer of the present invention addresses these issues while maximizing the quantity of debris filtered from the water.

Abstract: Fuel bundles for a nuclear reactor are disclosed, and in some embodiments include a first fuel element including thorium dioxide; a second fuel element including uranium having a first fissile content; and a third fuel element including uranium having a second fissile content different from the first fissile content. Nuclear reactors using such fuel bundles are also disclosed, including pressurized heavy water nuclear reactors. The uranium having the different fissile contents can include combinations of natural uranium, depleted uranium, recycled uranium, slightly enriched uranium, and low enriched uranium.

Abstract: A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in the fuel elements.

Abstract: An apparatus for use in making localized passive measurements of electromagnetic radiation emitted from an object located in a radioactive environment includes a hollow elongate conduit having a first end, a second end, and a reflective inner surface. The first end of the conduit is positionable in the radioactive environment proximate the object, and the second end of the conduit is positionable outside the radioactive environment. The conduit has at least one bend between the first end and the second end, such that light entering the first end of the conduit is reflected by the inner surface of the conduit at least once as it travels through the conduit before reaching the second end. A detector in optical communication with the second end of the conduit is configured to detect electromagnetic radiation that reaches the second end.

Abstract: A method for assaying a wall of a pressure tube for a nuclear reactor is disclosed. The wall has a matrix material and deuterium nuclei in the matrix material. The method includes: (a) transmitting gamma rays into the matrix material to induce photodisintegration of at least some of the deuterium nuclei, whereby reaction particles of the nuclei are emitted from the wall; (b) detecting at least some of the reaction particles emitted in step (a) using a particle detector; and (c) generating particle signals in response to detecting the particles in step (b).

Abstract: The invention relates to isotope separation methods, and methods for separating isotopes with low energy consumption, demonstrated using hydrogen isotopes. Also described are methods for enriching or depleting the isotope present in the hydrogen gas/vapour feed e.g. for tritium removal, tritium enrichment and deuterium enrichment, by arranging a series of cells in a cascaded configuration.

Abstract: A cross-over fluid coupling includes a first coupling end and a second coupling end. A plurality of first conduits have inner ends disposed toward the first coupling end and outer ends spaced apart from the inner end toward the second coupling end and being outboard of the inner end. A plurality of second conduits have outer ends that are disposed toward the first coupling end and positioned laterally outboard of the inner end of at least one of the first conduits, and inner ends that are spaced apart from the outer end toward the second coupling end in the axial direction and is laterally inboard of the outer end of the at least one of the first conduits.

Abstract: A conduit can include a sidewall and at least a first cavity can be disposed in the sidewall. The first cavity may include a first base surface portion and an opposing first cover surface portion disposed radially between the first base surface portion and the first inner surface so that a first portion of the sidewall is provided radially between the first cover surface portion and the inner surface. A first aperture may be in communication with the first cavity and may be axially spaced apart from the first cover surface portion. A first sensor may have a transducer portion insertable through the first aperture and positioned within the first cavity. The transducer portion may be disposed radially between the first base surface portion and the first cover surface portion and being axially spaced apart from the first aperture.

Abstract: A system for monitoring ionizing radiation in a target area, the system may include a first plurality of consumable nodes deployable within the target area to be exposed to the ionizing radiation. Each consumable node may be progressively damageable over a monitoring time as a result of exposure to the ionizing radiation. A base station may be operable to detect an amount of radiation damage sustained by the consumable nodes and to determine a dosage of ionizing radiation received by any one of the consumable nodes based on a pre-determined correlation between the dosage of ionizing radiation and the amount of radiation damage sustained by the consumable node.

Abstract: A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.

Abstract: A channel type heterogeneous reactor core for a heavy water reactor for burnup of thorium based fuel is provided. The heterogeneous reactor core comprises at least one seed fuel channel region comprising seed fuel channels for receiving seed fuel bundles of thorium based fuel; and at least one blanket fuel channel region comprising blanket fuel channels for receiving blanket fuel bundles of thorium based fuel; wherein the seed fuel bundles have a higher percentage content of fissile fuel than the blanket fuel bundles. The seed fuel channel region and the blanket fuel channel region may be set out in a checkerboard pattern or an annular pattern within the heterogeneous reactor core. Fuel bundles for the core are also provided.

Abstract: Fuel bundles for a nuclear reactor are described and illustrated, and in some cases includes fuel elements each having a first fuel component of recycled uranium, and a second fuel component of at least one of depleted uranium and natural uranium blended with the first fuel component, wherein the blended first and second fuel components have a first fissile content of less than 1.2% wt of 235U. Other fuel bundles are also described and illustrated, and include a first fuel element including recycled uranium, the first fuel element having a first fissile content of no less than 0.72 wt % of 235U; and a second fuel element including at least one of depleted uranium and natural uranium, the second fuel element having a second fissile content of no greater than 0.71 wt % of 235U.

Abstract: An apparatus for adhering a filament to a surface can include a body having a filament inlet port, at least a first filament outlet port spaced apart from the filament inlet port, and at least a first filament travel path extending between the filament inlet port and the first filament outlet port. A reservoir chamber can form a portion of the first filament travel path between the filament inlet port and the first filament outlet port and can contain a viscous adhesive material. Imparting relative axial movement between the body and a first filament can urge the first filament along the first filament travel path and through the reservoir chamber so that the first filament is coated with the viscous adhesive material when exiting via the first filament outlet port, for adhesion to the surface.

Abstract: A surface treating apparatus for treating an inner surface of a bore containing a shaft may include a body connectable to a drive apparatus and configured to movably receive a shaft extending through a bore, and at least one surface treating member connected to and movable with the body relative to the shaft, the at least one surface treating member sized to be inserted within an annular gap formed between the shaft and an inner surface of the bore and to bear against the inner surface of the bore when the shaft is received by the body.