| GE-Hitachi Nuclear Energy Americas LLC Patent applications |
| Patent application number | Title | Published |
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| 20120057992 | METHOD AND APPARATUS FOR A JET PUMP SLIP JOINT INTERNAL SEAL - 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. | 03-08-2012 |
| 20120032064 | METHOD AND APPARATUS FOR A BWR JET PUMP SUPPORT SYSTEM - 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. | 02-09-2012 |
| 20110299650 | APPARATUS AND METHOD FOR REPAIRING RISER PIPE ELBOW WELD IN BOILING WATER NUCLEAR REACTOR - 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. | 12-08-2011 |
| 20110299649 | ACOUSTIC LOAD MITIGATOR - 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. | 12-08-2011 |
| 20110252627 | Apparatus and Method for Repairing a Core Spray Line Elbow Weld Joint - An elbow clamp assembly structurally supports or replaces a connection between a main pipe and an elbow pipe. The elbow clamp assembly includes an upper clamp body and a lower clamp body securable on opposite sides of the main pipe in facing relation. The upper and lower clamp bodies are connected by a clamp bolt extendable through the main pipe. An elbow boss is securable to the elbow pipe, and a cross bolt is extendable through the elbow pipe and connected between the elbow boss and the clamp bolt. | 10-20-2011 |
| 20110240715 | WELDING PROCESS AND CORROSION-RESISTANT FILLER ALLOY AND CONSUMABLES THEREFOR - A nickel-based alloy and welding processes and consumables that use the alloy as a weld filler metal to fabricate, weld overlay, and repair components, including components of nuclear power plant reactors that contact the hot coolant water of the reactor. The nickel-based alloy consists of, by weight, 26 to about 30% chromium, 2 to about 4% iron, 2 to about 4% manganese, 2 to about 3% niobium, 1 to about 3% molybdenum, not more than 0.6% titanium, not more than 0.03% carbon, not more than 0.05% nitrogen, not more than 0.6% aluminum, not more than 0.5% silicon, not more than 0.01% copper, not more than 0.02% phosphorus, not more than 0.01% sulfur, with the balance nickel and incidental impurities. | 10-06-2011 |
| 20110217917 | AIR FILTRATION AND HANDLING FOR NUCLEAR REACTOR HABITABILITY AREA - A system for circulating and conditioning air within a nuclear reactor habitability area is provided. The system may include an upper plenum formed between a lowered ceiling partition within the habitability area and a ceiling of the habitability area and a lower plenum formed between a raised floor partition within the habitability area and a floor of the habitability area. The system can additionally include at least one recirculation air handling unit located within the habitability area, the at least one recirculation air handling unit operable to generate a recirculation air flow within the habitability area by circulating air between the lower and upper plenums absent any air carrying ductwork routed through the ceiling, floor or walls of the habitability area. | 09-08-2011 |
| 20110210228 | Apparatus and Method for Repairing a Core Spray Line Pipe Weld Joint - 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. | 09-01-2011 |
| 20100242660 | Manipulator for remote activities in a nuclear reactor vessel - A manipulator for remotely controlled underwater operation in a nuclear radiation environment to perform service activities at difficult to access regions of the reactor vessel is disclosed. The manipulator includes six degrees of freedom in its ability to move so that it can get past obstructions inside a reactor vessel to access and service remote locations in the vessel. The manipulator also includes a rotary drive for inserting and removing the manipulator into and from a reactor vessel and for rotating the manipulator within the vessel. It also includes an arm with two rotary joints and three pivot joints that can be deployed for better access to difficult to reach locations. The manipulator, which is remotely operated, can be used to manipulate a variety of tools to perform various service activities. The tools, which are attached to the end of the arm, include a water jet, a gripper, a cutter and a camera. | 09-30-2010 |
| 20100242247 | TELESCOPING TOOL ASSEMBLY AND METHOD FOR REFURBISHING WELDS OF A CORE SHROUD OF A NUCLEAR REACTOR VESSEL - An assembly adapted to access a weld extending circumferentially around a core shroud of a nuclear reactor, wherein the core shroud is contained in a pressure vessel reactor, the assembly including: a baffle plate rail having a lower surface adapted to abut a baffle plate in a gap between the core shroud and the pressure vessel reactor; a telescoping rail slidably coupled to an upper region of the baffle plate rail, and a reciprocating rail slidably coupled to an upper region of the telescoping rail, wherein the reciprocating rail includes at least one of a weld conditioning tool, a weld inspection sensor and a weld repair device. | 09-30-2010 |
| 20100032938 | Method and apparatus for repairing a core spray downcomer pipe slip joint coupling - A slip joint clamp is disclosed which structurally replaces cracked welded joints in the core spray downcomer slip joint coupling, which is part of the lower portion of internal core spray piping internal to a reactor vessel of a Boiling Water Reactor plant. The internal piping delivers core spray cooling water to the reactor core region. The clamp assembly consists of a primary clamp housing and a secondary clamp housing, which are rotationally joined together by a hinge assembly including a hinge pin. The clamp assembly is installed at a desired elevation relative to the downcomer slip joint, and then secured to the downcomer piping by installing coupling bolts and associated coupling bolt keeper nuts that hold the primary and secondary clamp housings in a facing relationship to one another around the downcomer slip joint. | 02-11-2010 |
| 20090307891 | Method and apparatus for remotely inspecting and/or treating welds, pipes, vessels and/or other components used in reactor coolant systems or other process applications - A tool is disclosed for remotely inspecting and/or treating welds, pipes, vessels and/or other components used in reactor coolant systems or other process applications to, among other things, mitigate stress corrosion cracking in the welds, pipes, vessels and/or other components. The tool is placed at the entrance to a pipe or vessel and walks into the pipe or vessel to a pre-selected weld, pipe or vessel location or other component. Upon reaching the pre-selected weld, pipe or vessel location or other component, the tool anchors itself, then advances an end effector to inspect and/or treat the pre-selected weld, pipe or vessel location or other component. | 12-17-2009 |
| 20090210169 | HAND-HELD SYSTEMS AND METHODS FOR DETECTION OF CONTAMINANTS IN A LIQUID - A method for detecting contaminants in a liquid is provided. The method can include filling at least a portion of a sample container interior chamber with a liquid sample and submerging a sensor probe of a hand-held portable sensing device in a liquid sample. The method can additionally include sensing an electrical conductivity of the liquid sample utilizing at least one conductivity sensor and automatically selecting a particular one of a plurality of contaminant concentration detection (CCD) algorithms based on the sensed conductivity. The method can further include setting a sensitivity of at least one ionic species sensor to a sensitivity level particular to the selected CCD algorithm and sensing non-desired contaminants in the liquid sample utilizing the at least one ionic species sensor. A concentration of the non-desired contaminant in the liquid sample is then determined in accordance with the selected CCD algorithm. | 08-20-2009 |
| 20090154636 | Chemical injection system and chemical delivery process/method of injecting into an operating power reactor - 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. | 06-18-2009 |
| 20090135988 | Fail-Free Fuel Bundle Assembly - A fuel bundle for a nuclear reactor core is provided. The fuel bundle may include a plurality of rods comprised of nuclear fuel rods and/or isotope production rods. Each rod includes a plurality of interconnected rod segments, wherein at least two of the rod segments of at least one rod have different outside diameters. The fuel bundle may additionally include a plurality of rod spacer grids securely retained between axially adjacent, interconnected rod segments. The rod spacer grids interconnected between axially adjacent rod segments form an array of substantially equally spaced rods. The fuel bundle may further include an elongate tubular channel in which the arrayed rods are housed. | 05-28-2009 |
| 20090135984 | GAMMA THERMOMETER AXIAL APPARATUS AND METHOD FOR MONITORING REACTOR CORE IN NUCLEAR POWER PLANT - 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, wherein the GT sensors are arranged asymmetrically along the first linear array; positioning a second linear array of GT sensors in a second instrument housing, wherein the GT sensors are arranged asymmetrically along the second linear array and wherein the second linear array of GT sensors is asymmetrical with respect to the first linear array of GT sensors; 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. Detector calibration can be accomplished by using the adjacent GT sensor, the closest GT sensor in the string (if the adjacent GT sensor is unavailable) or by using the GT sensor in a symmetric string that has a close axial height to the adjacent GT sensor. | 05-28-2009 |
| 20090135983 | Cross-Section Reducing Isotope System - An isotope production target rod for a power generating nuclear reactor is provided. The isotope production target rod can include at least one rod central body including an outer shell that defines an internal cavity and a plurality of irradiation targets within the internal cavity. The irradiation targets can be positioned in a spatial arrangement utilizing a low nuclear cross-section separating medium to maintain the spatial arrangement. | 05-28-2009 |
| 20090127854 | METHOD AND SYSTEM FOR REPAIRING A DOWNCOMER PIPE IN A CORE SPRAY FOR A NUCLEAR REACTOR - A slip joint assembly has been developed for a downcomer pipe in a core spray system of a nuclear reactor pressure vessel, the slip joint assembly including: a housing sleeve formed around a slip joint in the downcomer pipe, wherein an annular gap exists between an inside surface of the housing sleeve and the downcomer pipe; an upper wedge and a lower wedge insertable in the gap; a wedge bolt extending through the gap and extending through the upper wedge and lower wedge, wherein the bolt applies a force pulling the upper and lower wedge together to secure the housing sleeve to the downcomer pipe; an upper pin extending from the housing sleeve into an aperture of an upper section of the downcomer pipe, and a lower pin extending from the housing sleeve into an aperture of a lower section of the downcomer pipe. | 05-21-2009 |
| 20090095849 | Jet pump sensing line T-bolt clamp assembly - A remotely installable piping support attachment assembly employs a T-bolt type fastener for clamping a relatively smaller instrumentation pipe, e.g., the jet pump sensing line, to the wall of an adjacent structure. The attachment assembly includes a T-bolt, a split pipe clamp support, a ratchet nut with peripheral ratchet teeth, and a ratchet lock washer. When the nut is tightened on the threaded shank of the T-bolt, a top plate and an anchor of the split pipe clamp support are pressed together to clamp the jet pump sensing line therebetween. The top plate is defined by an L-beam folded spring plate comprised of first and second plate parts disposed generally in parallel and joined at a living hinge flex joint so that said plate parts each have a free end edge remote from said flex joint, the free end edges being spaced apart to define a gap therebetween without preload. | 04-16-2009 |
| 20090046825 | Protective coating applied to metallic reactor components to reduce corrosion products into the nuclear reactor environment - An insulating coating is applied to the metallic components in a nuclear reactor water environment to decrease and/or mitigate general corrosion and erosion-corrosion of the reactor component's metallic surfaces. Preferably, the coating is a 0.1 micron to 0.3 mm thin layer of an oxide coating such as titania (TiO | 02-19-2009 |
| 20090001229 | APPARATUS AND METHOD FOR REPAIRING RISER PIPE ELBOW WELD IN BOILING WATER NUCLEAR REACTOR - 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. | 01-01-2009 |
