Abstract: Disclosed is a device for performing pore size testing on a mesh wick. The device includes a housing and a tube positioned through the housing. The housing includes an internal surface. The tube includes an exterior surface. The exterior surface of the tube and the internal surface of the housing cooperatively define an internal cavity therebetween. The device further includes an inlet pipe extending from the housing. The inlet pipe connects to the internal cavity to allow a fluid to enter the internal cavity through the inlet pipe. The device further includes an expandable bladder positioned around a portion of the housing. The expandable bladder includes a first end and a second end. The portion of the housing is to allow the fluid to exit the internal cavity through the housing into the expandable bladder which causes the expandable bladder to expand.

Abstract: A tool for uncoupling and coupling an extension shaft assembly from a control element assembly of a nuclear reactor during reactor servicing is disclosed. The extension shaft assembly is transitionable between a coupled configuration where the extension shaft assembly is coupled to the control element assembly and an uncoupled configuration where the extension shaft assembly is uncoupled from the control element assembly. The tool comprises a support structure selectively attachable to the extension shaft assembly, a linear actuator, a microcontroller, a power source connector, a plunger shaft selectively attachable to the extension shaft assembly, and a sensor coupled to the microcontroller and the linear actuator. The sensor monitors a parameter indicative of a force experienced by the extension shaft assembly during at least one of a first actuation stroke or a second actuation stroke of a linear drive of the linear actuator.

Abstract: The present application relates to nuclear fuel claddings, and more particularly to zirconium alloy tubes with a ceramic covering. A first coating layer is applied to the ceramic covering. A second coating layer is over the first coating layer. The first coating layer includes Nb. The second coating layer includes Cr.

Abstract: A forming assembly configured to form a wick is disclosed. The forming assembly includes an expandable tube and a forming shell assembly. The expandable tube is hydraulically expandable to an expanded configuration. A wick mesh is configured to be wrapped about the expandable tube. The forming shell assembly includes a first forming shell comprising a first recess defined therein and a second forming shell comprising a second recess defined therein. The first recess and the second recess cooperate to define an outer diameter of the wick. The expandable tube and the wick mesh are positionable between the first recess and the second recess. The expandable tube and the forming shell assembly are configured to deform the wick mesh and form the wick based on the expandable tube hydraulically expanding towards the expanded configuration.

Abstract: An ultrasonic testing apparatus structured to perform an ultrasonic inspection on a workpiece. The ultrasonic testing apparatus comprises an ultrasonic testing probe structured to generate an ultrasonic output directed toward the workpiece and to receive an ultrasonic input from the workpiece that is responsive to the output; a couplant delivery system comprising a couplant supply, the couplant delivery system further comprising an actuator which, when operated, is structured to apply from the couplant supply an amount of a couplant to at least one of the workpiece and the ultrasonic testing probe; and a control apparatus electrically connected with the ultrasonic testing probe and with the couplant delivery system, the control apparatus being structured to receive the ultrasonic input and being further structured to operate the actuator. A couplant delivery system that is operable with an ultrasonic testing apparatus that is structured to perform an ultrasonic inspection on a workpiece.

Abstract: A power sensor system for monitoring a subcritical neutron generator is provided. The power sensor system comprises a self-powered sensor insert. The self-powered sensor insert comprises an insert thimble and a detector assembly. The insert thimble includes an outer housing, a power generator configured to produce an electrical power based on an incident radiation and a first electrical interface electrically connected to the power generator. The detector assembly includes a solid state radiation detector able to provide a detector signal directly proportional to a neutron flux level, a transmitter configured to wirelessly output a transmitter signal based on the detector signal and a second electrical interface configured to electrically couple to the first electrical interface. A power monitor system comprising a power sensor system and a control system and a method for optimizing a subcritical neutron generator are also provided.

Abstract: A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pure and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

Abstract: A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

Abstract: A heat exchanger for a nuclear reactor is provided. The heat exchanger comprises a first layer for flowing a first process fluid and a second layer for flowing a second process fluid. The first layer is comprised of a first material and the second layer is comprised of a second material differing in composition from the first material. The first layer and the second layer are stacked on each other in a core of the heat exchanger and the first layer and the second layer are bonded to each other. A heat exchanger for a nuclear reactor and a method for producing a heat exchanger are also provided.

Abstract: An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.

Abstract: A nuclear fuel rod includes a cladding comprising an interior region. A pressure transmission apparatus is configured to measure pressure in the interior region. Fuel pellets and a resonant electrical circuit are in the interior region. The resonant electrical circuit is configured to generate a pulse that travels wirelessly from the interior region through the cladding. A frequency of the pulse varies based on pressure measured by the pressure transmission apparatus. The frequency of the pulse is indicative of the pressure within the interior region.

Abstract: A nuclear reactor comprising a vessel and a micro-channel heat exchanger is disclosed. The vessel houses coolant defining a maximum level within the vessel, and the micro-channel heat exchanger is partially submerged below the maximum level. The micro-channel heat exchanger comprises a core, a plurality of primary channels, and a plurality of secondary channels. The core comprises a top face, a bottom face disposed opposite the top face, a first side face extending between the top face and the bottom face, and a second side face disposed opposite the first side face. The plurality of primary channels extends through the core from a primary inlet of the first side face to a primary outlet of the second side face. The plurality of secondary channels extends through the core among the plurality of primary channels from a secondary inlet of the top face to a secondary outlet of the top face.

Abstract: Disclosed is a nuclear reactor system for use with a power grid. The nuclear reactor system comprising a nuclear reactor, an energy storage system coupled to the nuclear reactor, and a control circuit coupled to the nuclear reactor and the energy storage system. The control circuit is configured to monitor a power demand of the power grid, monitor a power output generated from the nuclear reactor, detect a change in the power demand, cause the energy storage system to temporarily compensate for the change in the power demand, and adjust the power output based on the change in the power demand.

Abstract: An ultrasonic testing probe operable to perform an ultrasonic inspection on a workpiece, the workpiece having an interior region. The testing probe comprises a support; an ultrasonic testing element that is structured to generate an ultrasonic output that is directed toward the workpiece and to receive an ultrasonic input from the workpiece that is responsive to the ultrasonic output, the ultrasonic testing element being movably situated on the support; a motor apparatus structured to be electrically connected with a control apparatus, the motor apparatus comprising a motor that is connected with the ultrasonic testing element and is structured to rotate the ultrasonic testing element with respect to the support; and a bladder that is structured to be movable between an initial state and an expanded state, the expanded bladder structured to be engaged with the workpiece within the interior region and to center the support in the interior region.

Abstract: A manipulator configured to navigate a heat exchanger including a plurality of tubes extending through a tubesheet is disclosed herein, the manipulator including a first end effector, a second end effector, and an articulation assembly. The first end effector is configured to accommodate an instrument configured to service the heat exchanger and includes a first actuator configured to extend a first gripper into a tube of the plurality of tubes. The second end effector includes a second actuator configured to extend a second gripper into a tube of the plurality of tubes. The first and second gripper are configured to secure the manipulator to the tubesheet, and, when the second gripper is securing the manipulator to the tubesheet, the articulation assembly is configured to enable the first end effector to move relative to the second end effector in a plane that is parallel to the tubesheet.

Abstract: A nuclear battery is provided. The nuclear battery comprises a radiation source layer, a first electrical insulator layer, a casing layer, a first electrode, and a second electrode. The radiation source layer comprises a composition configurable to emit beta radiation. The first electrical insulator layer is disposed over the radiation source layer. The casing layer is disposed over the first electrical insulator layer. The casing layer comprises a composition configured to inhibit traversal of beta radiation. The first electrode is in electrical communication with the radiation source layer. The second electrode is in electrical communication with the casing layer. A voltage potential is present between the first electrode and the second electrode when the radiation source layer emits beta radiation.

Abstract: Devices, systems, and methods to produce Ac-225 from Ra-226 using gamma-radiation generator are disclosed herein. The gamma radiation generator can utilize an electronic neutron generator or a nuclear reactor to produce high energy prompt-capture gamma-radiation. The Ra-226 is irradiated by the gamma radiation to produce Ra-225, which decays to produce Ac-225. The method of using electronic neutron generator and an irradiation target material such as Gd-157 to produce high energy gamma radiation without using a continuously decaying radioisotope such as Co-60 could significantly reduce the cost and increase the safety associated with the production of high energy gamma radiation and Ac-225.

Abstract: Methods of manufacture for nuclear batteries are provided. The method comprises inserting a radiation source material into a cavity defined within a first component to form a radiation source layer. The first component comprises a first electrical insulator layer defining the cavity and a first casing layer disposed over the first electrical insulator layer. The method comprises contacting the first casing layer with a second casing layer of a second component to form an assembly. The second component comprises a second electrical insulator layer and the second casing layer disposed in contact with the second electrical insulator layer. The method comprises swaging the assembly to form the nuclear battery.

Abstract: Disclosed is a nuclear reactor, comprising: a canister, a nuclear reactor core housed inside of the canister, and a controlled temperature housing attached to the canister. The nuclear reactor core comprises a control drum and a shaft extending from the control drum and out of the nuclear reactor core. Heat generated by the nuclear reactor core enters the controlled temperature housing. The controlled temperature housing comprises a proximal end attached to the canister, a first internal plate spaced from and positioned distal to the proximal end, a second internal plate spaced from and positioned distal to the first internal plate, and a motor mounted to the second internal plate. The shaft enters the controlled temperature housing through the proximal end and extends to the motor. The controlled temperature housing is to passively maintain the motor at a temperature equal to or below a predetermined temperature threshold.

Abstract: An adjustable core assembly for a nuclear reactor is disclosed herein. The adjustable core can include a plurality of reactivity control cells configured to accommodate a reactivity control rod, and a plurality of unit cells. The plurality of unit cells defines a radial dimension corresponding to an initial power output of the core. Each unit cell of the plurality of unit cells is configured to accommodate fuel configured to generate energy and a heat pipe configured to transfer thermal energy away from the core. Each unit cell of the plurality unit cells can be coupled to an adjacent unit cell in a radial direction, thereby altering the radial dimension, wherein the altered radial dimension corresponds to an adjusted power output of the core, and wherein the adjusted power output of the core is different than the initial power output of the core.