Abstract: A wet filter for a nuclear reactor primary containment vent that employs an inclined manifold having a plurality of outlets that communicate through a first set of metal fiber filters submerged in a pool of water enclosed within a pressure vessel. A demister suspended above the pool of water to remove any entrained moisture in the filtered effluent before being passed through a second stage of higher density, dry, metal fiber filters connected to a second manifold that communicates with an outlet on the pressure vessel that is connected to an exhaust passage to the atmosphere.

Abstract: A remote heat removal system that pumps a secondary fluid from a remote reservoir through a secondary side of a heat exchanger in heat exchange relationship with a primary fluid to be cooled. The secondary fluid drives a motive device that drives the primary fluid through the primary side of the heat exchanger.

Abstract: A delivery device that is usable in a laser peening operation emits a columnar flow of a fluid that contains therein a beam of electromagnetic energy. The beam is retained within the interior of the flow of fluid since the total internal reflectivity of the flow is sufficient to do so. The flow of fluid that serves as a conduit for the beam also itself impinges on a workpiece and thus contains and washes away the plasma that forms from a laser peening operation, and this resists the plasma from reaching and possibly damaging the delivery device. The carrying of the beam in the columnar flow of fluid avoids the need to maintain a fixed distance between the delivery device and the workpiece, which simplifies the movement by a robotic manipulator of the delivery device along a non-planar surface of a workpiece during a laser peening operation.

Abstract: A server-based nuclear containment operations system can be used to monitor structures, systems, components, and personnel within the containment building of a nuclear power facility. The disclosed and claimed concepts relate generally to a method for utilizing near field communication (NFC) on a mobile client device having the dynamic capabilities of a logic-based computerized procedures system (CPS). The client permits the execution of procedures remotely in the field while monitoring the real-time current state and operation of the systems, components, and sensors of a large facility such as a nuclear power plant. This system consists of a client and server application which provide real-time monitoring of procedure adherence and place keeping, facility clearance information, and work order administration (including tracking an operator's procedure adherence) and further provides a capability for operator input.

Abstract: A method of removing the upper internals assembly from a nuclear reactor pressure vessel for refueling that simultaneously disconnects two or more of the in-core instrument thimble assemblies from the reactor vessel penetrations through which their signal cables extend. The signal cables are connected to the penetrations with an electrical connector that supports the two or more in-core instrumentation thimble assembly signal leads. Before the electrical connector is disconnected, water in the vessel is lowered below the connection so that the process is performed in a dry environment.

Abstract: An integral pressurized light water reactor having most of the components of a primary side of a pressurized water reactor nuclear steam supply system housed in a single pressure vessel with a pressurizer separated from the remaining reactor system by a surge separator having multiple layers of separated steel plates with a number of concentric baffles extending therebetween. A circuitous flow path is provided through and between the plates and concentric baffles and a relatively stagnant pool of coolant is maintained within an innermost zone between the plates to provide thermal isolation.

Abstract: A delivery system for remotely driving an eddy current probe through the tubing of a heat exchanger. The system uses a flexible shaft and air pressure to move an inspection probe through the heat exchanger tubes. The flexible shaft initially drives the probe through a sealed conduit to deliver the probe to the tube end at which point a seal on the shaft near the probe head contacts the tube inner surface allowing a buildup of air pressure behind the seal, thus driving the probe through the tube.

Abstract: An expansion gap radiation shield is formed from a flexible container housing a radiation shielding fluid, that is located within a variable gap in permanent shielding. The invention reduces radiation dose rates outside the gap when the radiation sources are located on the opposite side of the gap. The device accommodates varying gap sizes with no loss of shielding capability.

Abstract: A supercritical carbon dioxide power generation Brayton cycle system and method that employs an alternate heat recuperation method and apparatus that utilizes switched banks of bead filled tanks to accumulate and recover the thermal energy of the two streams of working fluid in such a way that the variable thermal properties of the supercritical carbon dioxide can be accommodated without significant loss of thermal efficiency.

Abstract: A method of providing an end-capped tubular ceramic composite for containing nuclear fuel (34) in a nuclear reactor involves the steps of providing a tubular ceramic composite (40), providing at least one end plug (14, 46, 48), applying (42) the at least one end plug material to the ends of the tubular ceramic composite, applying electrodes to the end plug and tubular ceramic composite and applying current in a plasma sintering means (10, 50) to provide a hermetically sealed tube (52). The invention also provides a sealed tube made by this method.

Abstract: The present invention relates generally to a process for a pressurized water reactor. The pressurized water reactor includes a primary circuit and a reactor core. The process includes adding a sufficient amount of an organic compound to coolant water passing through the primary circuit of the pressurized water reactor. The organic compound includes elements of carbon and hydrogen for producing elemental carbon.

Abstract: This invention concerns robotic systems and is specifically concerned with an improved apparatus and method for remotely positioning a sensor, such as an ultrasonic probe, in limited access areas within a nuclear reactor. The apparatus includes a bottom frame and a top cover which is substantially aligned with and positioned above the bottom frame. A sensor is connected to the top cover and linear rails are connected to the bottom frame in a parallel relationship. There is a mechanism movably connected to the first and second linear rails in order to allow horizontal travel of the top cover. Further, there is at least one cable connected to the sensor and a power source, signal source or receiver.

Abstract: A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

Abstract: This invention generally concerns robotic systems and is specifically concerned with an improved apparatus and method for inspecting nuclear reactor components in limited access areas, such as, the core annulus, core spray and feedwater sparger regions of a nuclear reactor. This invention includes an apparatus for remotely operating and positioning at least one inspection device for inspecting at least one component in an annulus region of a reactor pressure vessel of a nuclear power plant. The apparatus includes a track, a braking system and a frame assembly which has a frame movably connected to the track, at least one mast assembly and at least one mast positioning assembly. The at least one inspection device is attached to the at least one mast assembly. In certain embodiments, the at least one mast assembly includes a mast that is capable of becoming rigidly stable in both an extended tube form and a retracted rolled form.

Abstract: The invention relates to systems and methods for verifying complete analysis coverage in a steam generator tube inspection. The analysis is conducted by an automated analysis process. The process includes setup and analysis functions. Information is entered into the setup function to identify abnormalities to be inspected and to model the steam generator tubes. The verification includes employing a software verification program to detect and identify a gap within analysis coverage for a particular abnormality or set of abnormalities for which the steam generator tube is inspected, in a particular portion of the steam generator tube.

Abstract: A system and method for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant. In certain embodiments of this invention, one or more neutron detectors are operable to generate signals resulting from neutron interactions in the spent fuel pool, a counting device counts the signals which are generated by the one or more neutron detectors, a connecting means electrically connects the one or more neutron detectors to the counting device, a signal analyzer is used to determine reactivity of the fuel assemblies in the spent fuel pool based on the counted signals, a power supply provides power for the neutron detectors, the counting device and the system analyzer, and a software code containing an axial flux curve index is used to correlate the counted signals to determine the subcriticality of the spent fuel pool.

Abstract: A method includes detecting on an ongoing basis the currently existing dose rates while a worker is performing a maintenance or other operation within the RCA, and visually outputting information that pertains to the ionizing radiation to which the worker is being exposed during the operation. The information that is visually output can include information such as the current dose rate and the overall dose to which the worker has been subjected, but can additionally include information such as the time remaining before which the worker will have been exposed to the maximum allowable dose. Furthermore, it is possible for the visual display to output visual indicia that represent a comparison the exposure to ionizing radiation that had been planned as a function of time prior to the operation being commenced with the actual exposure to ionizing radiation as the operation is performed.

Abstract: A magneto-rheological filter/reflector that controls the transmissivity of any form of electromagnetic or particulate radiation through the filter by varying discrete electromagnetic fields across a magneto-rheological fluid. In one embodiment, the filter/reflector controls the rate of the nuclear reaction within the core of a reactor without any moving parts.

Abstract: An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.

Abstract: A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days.