Abstract: A portable detection apparatus includes a fluid inlet to acquire a stream of fluid, a fluid outlet and a fluid flowpath therebetween. A pump circulates the fluid through the fluid flowpath. A gamma spectrometer and a mercury analyzer engage the fluid flowpath to analyze and detect radiation emitted by the fluid. A filter trap is in the fluid flowpath downstream from the gamma spectrometer and the mercury analyzer. The filter trap includes a valve assembly and at least a first and second filter for collecting gaseous constituents from the fluid. Each filter is removably connected to the first valve assembly. The valve assembly has a first configuration, in which the first filter is fluidly connected to the fluid flowpath and the second filter is fluidly isolated from the fluid flowpath, and a second configuration, in which the second filter is fluidly connected to the fluid flowpath and the first filter is fluidly isolated from the fluid flowpath.

Abstract: With a water, particulate and fibre mixture, a method of quantifying fibre content may include providing a sample of the mixture, filtering the sample to produce a particulate and fibre mixture, burning the particulate and fibre mixture to produce a fibre sample, and dissolving the fibre sample to produce a fibre solution. The fibre solution may be analyzed to determine an elemental content of the fibre solution. The elemental content may be compared to a known elemental content to estimate the fibre content.

Abstract: A regulator apparatus for distributing a fluid may include a charging valve assembly and a flow multiplier assembly. In a recharge mode, a valve of the charging valve assembly is in an open position, and the fluid is received in a second cylinder of the flow multiplier assembly, causing first and second pistons of the flow multiplier assembly to move in a first direction. In a purge mode, the valve is in the seated position, and the fluid is received in a first cylinder of the flow multiplier assembly, causing the first and second pistons to move in a second direction, and discharging an outlet flow through an outlet of the flow multiplier assembly. The second cylinder may have a bore cross sectional area that is greater than a bore cross sectional area of the first cylinder. Apparatuses disclosed herein may be implemented in a circumferential sampling tool.

Abstract: A portable detection apparatus can include a housing, a first detector for detecting ionizing radiation from a first subject and a second detector within the housing for the detecting the background radiation. A shield within the housing can surround the first and second detectors and define a shield aperture around the first and second detectors for radiation from the subject to enter the housing. A radiation blocking member can substantially block at least a portion of the ionizing radiation from reaching the second detector, whereby radiation detected by the second detector comprises substantially only the background radiation. A processor module can be connected to the first and second detectors for determining the amount of ionizing radiation detected by the first detector attributable to secondary radiation.

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: The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application for 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. Filtering of the debris is realized with the component known as “strainers”. There are restrictions on the space available for installing strainers. The vaned filtering element, for example a vaned fin, of the present invention is designed to reduce the space required for strainer installation by increasing strainer surface area per unit volume, while maximizing the quantity of debris that can be filtered from the water.

Abstract: A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

Abstract: A method of measuring ionizing radiation may include the steps of: a) creating charged particles; b) causing the charged particles to generate the electrons; c) collecting at least a portion of the multiplied free electrons using at least two anode pads provided within the chamber, each anode pad producing a corresponding anode output signal, to provide higher sensitivity; and d) recording each anode output signal.

Abstract: Processes and devices useful in the application of coatings (14) to the interior of tubes (10) are described. Such processes (40, 400) may include applying a layer (20) of coating fluid (18) to the internal surface (16) of the tube (10) and passing a smoothing member (22) through the tube (10) at a distance from the internal surface (16). The viscosity of the coating fluid (18) may be selected so that the layer (20) of coating fluid (18) has a thickness substantially equal to or in excess of a predetermined wet film thickness (Twf) correlated to a desired final thickness (Tf) of the coating (14). The distance between the smoothing member (22) and the internal surface (16) may substantially correspond to the predetermined wet film thickness (Twf). The smoothing member (22) may smooth the coating fluid (18) and remove coating fluid (18) in excess of the wet film thickness (Twf) from the internal surface (16).

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: A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.

Abstract: A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.

Abstract: A controller for producing a nuclear reactor shutdown system trip signal in response to at least one detector signal. The controller includes a signal conditioning module receiving the at least one detector signal and outputting a measured flux signal. A rate module generates a rate signal from the measured flux signal. A comparator circuit compares the rate signal to a trip setpoint and generates a first trip signal.

Abstract: An annulus spacer for a fuel channel assembly of a nuclear reactor, and method of manufacturing an annulus spacer. The fuel channel assembly includes a calandria tube and a pressure tube positioned at least partially within the calandria tube. The annulus spacer includes a garter spring configured to surround a portion of the pressure tube to maintain a gap between the calandria tube and the pressure tube. A girdle wire is positioned substantially within the garter spring and configured to form a loop around the pressure tube. The girdle wire includes a first segment and a second segment that overlaps the first segment to form an overlap, the overlap extending between approximately 45 degrees and approximately 135 degrees to reduce the possibility of girdle wire twisting.

Abstract: A portable detection apparatus can include a housing, a first detector for detecting ionizing radiation from a first subject and a second detector within the housing for the detecting the background radiation. A shield within the housing can surround the first and second detectors and define a shield aperture around the first and second detectors for radiation from the subject to enter the housing. A radiation blocking member can substantially block at least a portion of the ionizing radiation from reaching the second detector, whereby radiation detected by the second detector comprises substantially only the background radiation. A processor module can be connected to the first and second detectors for determining the amount of ionizing radiation detected by the first detector attributable to secondary radiation.

Abstract: A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section.

Abstract: An apparatus for holding radioactive objects includes a base and a central pillar extending upwardly between a bottom end coupled to the base and a top end above the base. A plurality of inner segments are spaced around the central pillar, and a plurality of outer segments are spaced around the inner segments to form pairs. The inner segments, the outer segments and the central pillar may be coupled together to permit limited radial movement of at least one of the segments of each pair. Each pair may define a generally vertical, object-receiving channel arranged between the inner and outer segment of the pair. The segments of each pair may be adapted to bear against an object in the channel of the pair to laterally restrain the object and facilitate heat transfer from the object.

Abstract: The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube within a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends.

Abstract: An electrochemical cell for producing hydrogen gas and cupric chloride. The cell comprises: an anode compartment comprising an anode for disposition in an anolyte, wherein the anolyte is cuprous chloride in hydrochloric acid; a cathode compartment comprising a cathode, wherein the cathode comprises an electrocatalyst; a plurality of ion exchange membranes disposed between the anode compartment and the cathode compartment; and at least one center compartment defined by a pair of said ion exchange membranes and comprising at least one element for removal or sequestering of copper ions that cross at least one of said membranes from the anode compartment. Also described is a method for CuCl/HCl electrolysis in the production of hydrogen using the electrochemical cell.

Abstract: A method of collecting 3He from a nuclear reactor may include the steps of a) providing heavy water at least part of which is exposed to a neutron flux of the reactor, b) providing a cover gas in fluid communication with the heavy water, c) operating the nuclear reactor whereby thermal neutron activation of deuterium in the heavy water produces tritium (3H) and at least some of the tritium produces 3He gas by ?? decay and at least a portion of the 3He gas escapes from the heavy water and mixes with the cover gas, d) extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the 3He gas and e) separating the 3He gas from the outlet gas stream.