Abstract: A fuel bundle flow limiter according to a non-limiting embodiment of the present invention may include a plurality of base sections, wherein each of the plurality of base sections has at least one opening. A plurality of channels may separate the plurality of base sections. A plurality of vertical webs may extend from the plurality of base sections. A locking tab may be disposed in at least one of the plurality of vertical webs. By using the flow limiter, the moisture carry over (MCO) level at the exit of the fuel bundle may be decreased, thereby reducing radiation exposure to plant operators and reducing damage to reactor equipment.

Abstract: A method and apparatus for securely fastening a pipe collar or a bracket to a riser pipe of a boiling water reactor (BWR) jet pump assembly. A pipe plug assembly includes an angled pipe plug that acts as a wedge to expand a bushing assembly as the pipe plug is drawn into the overall pipe plug assembly. Expansion of the bushing assembly allows a tight tolerance to exist between an outer diameter of the pipe plug and an inner diameter of the collar/bracket and riser pipe. Expansion of the bushing assembly allows a straight hole to be match drilled into the collar/bracket and riser pipe, thereby avoiding a more complicated tapered hole to be drilled into the collar/bracket and riser pipe. An ensuing tight fit between the pipe plug assembly, the collar/bracket and the riser pipe mitigates vibration of components and minimizes leakage to acceptable levels for use in the flooded environment of the annulus region where the jet pump assembly exists in the BWR.

Abstract: A method and apparatus for repairing and/or reinforcing a Boiling Water Reactor (BWR) jet pump riser pipe. The repair includes attaching two collars to the riser pipe using match drilling to drill holes through the collars and the riser pipe and plugging the holes with expandable plugs. Support columns are attached to the collars. Brace supports are slideably attached to the support columns. Gaps between each brace support and its respective collar are then narrowed as ratchet bolts may apply a force that pulls downward on an upper collar and pulls upward on a lower collar, thereby exerting a compression force on the riser pipe. A clamp assembly may also be located between the two collars that applies a hoop force on the riser pipe.

Abstract: A flow limiter may include a head and a fin extending from a bottom of the head. The head may include a side surface having at least one first hole and the side surface may be symmetric about a first axis. The fin may include at least one second hole and the at least one second hole may have an axis substantially perpendicular to the first axis. The flow limiter may be inserted into a support casting that may interface with a nuclear fuel bundle to reduce the flow of water to the nuclear fuel bundle thereby reducing a moisture carry over (MCO) level at an exit of a fuel bundle of a nuclear reactor.

Abstract: Slip joint clamps are installed against guide ears of diffusers at jet pump slip joints. Clamps may prevent vibration and/or movement in the slip joint while not being rigidly attached to the diffuser. Clamps include a compression flipper pressing against a guide ear of the diffuser in a substantially radial direction, a biasing member between the compression member and guide ear that presses the flipper against the guide ear, and supporting structures that hold the flipper and biasing member to the inlet mixer about the guide ear. Systems of slip joint clamps are installed against several guide ears of a single diffuser. Each clamp may radially stabilize the diffuser and inlet mixer while permitting upward relative movement of the inlet mixer. Placement and tensioning of clamps in such systems may be varied so as to prevent or reduce vibrations and/or oscillations between an inlet mixer and diffuser.

Abstract: An embodiment of the present invention may reduce the level of vibration experienced by a line, such as, but not limiting of, a pipe, a cable, tubing, or the like, that is connected to at least one separate structure. For example, but not limiting of, the structure includes: a reactor pressure vessel, a sparger pipe, steam generator, a pipe, a pressure vessel, a heat exchanger, a pump, a condenser, a tank, or the like. An embodiment of the present invention may provide support and a preload to the line at a new location or may replace an existing support, such as, but not limiting of, a weld; which may alter the natural frequencies to avoid resonance from occurring when the structure(s) is excited.

Abstract: A clamping device supports or structurally replaces a weld joint between connected pipes. The clamping device includes an upper clamp body and a lower clamp body securable on opposite sides of the connected pipes in facing relation, and at least one clamp bolt connecting the upper and lower clamp bodies and extendable through the connected pipes. One of the upper and lower clamp bodies has at least one shaped depression, which receives a complementary shaped clamp bolt nut engageable with the clamp bolt. The shaped depression prevents rotation of the clamp bolt nut.

Abstract: A method for collecting data regarding the operating condition of a nuclear reactor core including: positioning a first linear array of gamma thermometer (GT) sensors in a first instrument housing; positioning a second linear array of GT sensors in a second instrument housing, wherein the GT sensors are arranged asymmetrically along the linear arrays and the second linear array is asymmetrical with respect to the first linear array; positioning the first instrument housing in the reactor core at a first core location and positioning the second instrument housing at a second core location symmetrical with respect to the first core location; collecting core condition data from at least one of the GT sensors in the first linear array of GT sensors, and applying the collected core condition data as data collected from the second linear array.

Abstract: An embodiment of the present invention takes the form of an apparatus or system that may reduce the level of vibration experienced by an inlet riser or other similar object within a reactor pressure vessel. An embodiment of the present invention may eliminate the need for welding the riser brace to the inlet riser. An embodiment of the present invention provides at least one riser brace clamp that generally clamps the riser brace to the inlet riser. After installation, the riser brace clamp may lower the amplitude of, and/or change the frequency of, the vibration experienced by the inlet riser.

Abstract: A method and apparatus for providing a Boiling Water Reactor (BWR) jet pump slip joint internal seal in the interface between an inlet mixer and a diffuser of a jet pump assembly. The internal seal provides an effective means of mitigating leakage and slip joint flow induced vibration (FIV) between the inlet mixer and diffuser to reduce damage to many of the jet pump assembly components that may otherwise be damaged by FIV. A metallic seal of the slip joint internal seal flares out to conform the internal seal to a range of gap sizes, and may be compressed or spring back to nominal dimensions as thermal expansion and contraction occurs. The internal seal is also self-expanding/self-tightening, as the internal seal flares further outward as a result of the internal pressure caused by flowing fluids in an operating jet pump assembly.

Abstract: A support clamp assembly for mechanically securing a thermal sleeve to an elbow conduit in a jet pump of a nuclear reactor vessel, the support clamp assembly including: a tension shaft having a first end extendable through an opening in a sidewall of the elbow conduit and an opposite end with a head; a cruciform assembly having a base with an opening to receive the tension shaft and to abut the head of the shaft, wherein the cruciform assembly seats in the thermal sleeve; a boss slidable over the first end of the tension shaft and having a curved surface seating an outside surface of the elbow conduit, and a coupling device engaging the first end of the tension shaft and abutting the boss, wherein the coupling device places the tension shaft under tension to secure the cruciform assembly to the thermal sleeve and the boss to the elbow conduit.

Abstract: A method and apparatus for applying a lateral restraining force to a diffuser or an inlet mixer of a Boiling Water Reactor (BWR) jet pump restrainer assembly, to pull the diffuser or inlet mixer toward a centerline of a riser pipe. The lateral restraining force may be applied to just a diffuser, or just an inlet mixer, or both. Clamps are attached to the diffuser or inlet mixer, and alternatively to the riser pipe, and draw bolts are connected to the clamps to provide the necessary restraining force. The lateral restraining force either mitigates damage and repair to a conventional jet pump restrainer assembly, or alternatively is used in lieu of a jet pump restrainer assembly.

Abstract: A method of inspecting, performing maintenance on, or repairing a nuclear reactor may include operatively connecting a fixing device, a first track, an arm including one or more second tracks, and an effector to form an apparatus; inserting the apparatus into the reactor; fixing the apparatus within the reactor; and operating the apparatus. At least one of the one or more second tracks may include at least three track sections. The arm may have a contracted length. The arm may have an expanded length. The expanded length may be greater than two times the contracted length. The first track may include one or more motors configured to move the arm relative to the first track. A method of operating a reactor may include shutting down; inspecting, performing maintenance on, or repairing the reactor; and starting up the reactor.

Abstract: Example embodiments relate to methods of controlling hydrogen concentrations in an offgas system of a nuclear reactor by passive air injection. A method according to a non-limiting embodiment may include passively injecting ambient air through the hydrogen water chemistry system into an existing offgas line of the offgas system. The offgas line is configured to transport non-condensable gases, including hydrogen, from a condenser to a recombiner. As a result of the passive air injection, the combined flow of hydrogen and oxygen react in the recombiner to form water vapor, thereby reducing the hydrogen concentration of the offgas exiting the recombiner.

Abstract: Example embodiment damping devices may include a housing capturing a piston. The housing may be filled and/or able to be filled with a damping fluid compatible with the nuclear reactor coolant, so that a leak from the housing or coolant passing into the housing does not damage the reactor or example embodiment devices. Example embodiments may further include one or more springs that provide an elastic force opposing movement between the piston and housing. A shaft of the piston and an end of the housing may be connected to two nuclear reactor components with relative motion or vibration to be damped. Example methods may use example embodiment damping devices to reduce and/or prevent relative motion and vibration among components of a nuclear reactor.

Abstract: A vane configuration for a steam dryer according to an example embodiment of the invention may include a plurality of primary vanes arranged in a radial pattern around (and spaced apart from) a center line. Each of the plurality of primary vanes may be a primary corrugated sheet having alternating primary ridges and primary furrows. As a result, adjacent primary vanes may define a winding flow path, the flow path having an entrance and an exit relative to the center line. The cross-sectional area of the flow path may decrease, increase, or remain constant from the entrance to the exit.

Abstract: A support clamp assembly for mechanically securing a thermal sleeve to an elbow conduit in a jet pump of a nuclear reactor vessel, the support clamp assembly including: a tension shaft having a first end extendable through an opening in a sidewall of the elbow conduit and an opposite end with a head; a cruciform assembly having a base with an opening to receive the tension shaft and to abut the head of the shaft, wherein the cruciform assembly seats in the thermal sleeve; a boss slidable over the first end of the tension shaft and having a curved surface seating an outside surface of the elbow conduit, and a coupling device engaging the first end of the tension shaft and abutting the boss, wherein the coupling device places the tension shaft under tension to secure the cruciform assembly to the thermal sleeve and the boss to the elbow conduit.

Abstract: A system for reducing an acoustic load of a fluid flow includes a first pipe to carry the fluid flow; a standpipe connected to the first pipe at an opening in the first pipe; and a standpipe flow tripper provided in the standpipe. The flow tripper includes an edge extending through the opening into the flow on a downstream side of the opening. A method of reducing an acoustic load of a standing wave in a standpipe connected to a first pipe configured to carry a flow includes disrupting the flow in the first pipe at a downstream side of an opening in the first pipe to which the standpipe is connected.

Abstract: A system for reducing an acoustic load of a fluid flow includes a first pipe to carry the fluid flow; a standpipe connected to the first pipe at an opening in the first pipe; and a standpipe flow tripper provided in the standpipe. The flow tripper includes an edge extending through the opening into the flow on a downstream side of the opening. A method of reducing an acoustic load of a standing wave in a standpipe connected to a first pipe configured to carry a flow includes disrupting the flow in the first pipe at a downstream side of an opening in the first pipe to which the standpipe is connected.

Abstract: An injection system designed to deliver a chemical solution into a reactor through feedwater system taps during normal operating condition of a power reactor is disclosed. The process of delivery is via positive displacement pumps. Injection of chemical is in a concentrated solution form, which is internally diluted by the system prior to discharging from the skid. The injection system minimizes chemical loss due to deposition on the transit line, enables a higher concentrated solution to be used as the injectant, eliminates the time consuming laborious process of chemical dilution, raises chemical solution to the pressure required for injection, prevents solid precipitations out of solution at the injection pump head through the use of a flush solution, and deposits fresh chemical on new crack surfaces that develop during a power reactor start-up, shutdown and operation.