Abstract: A jet pump beam bolt locking assembly includes a locking sleeve having a plurality of ratchet teeth extending around the periphery of a base portion, and a lock plate having a beam bolt opening, and an integral beam spring arm having a plurality of ratchet teeth extending from at least a portion of a side of the spring arm. The spring arm ratchet teeth are sized to mesh with the locking sleeve ratchet teeth. The lock plate also includes a lip extending at least partially around the beam bolt opening which captures the locking sleeve. The spring arm is movable between a first position where a lock plate detent is positioned in a spring arm notch which permits engagement of the ratchet teeth, and a second position where the side of the spring arm is in contact with the detent which disengages the ratchet teeth to permit loosening of the beam bolt.

Abstract: A jet pump beam bolt locking assembly includes a locking sleeve having a plurality of ratchet teeth extending around the periphery of a base portion, and a lock plate having a beam bolt opening, and an integral beam spring arm having a plurality of ratchet teeth extending from at least a portion of a side of the spring arm. The spring arm ratchet teeth are sized to mesh with the locking sleeve ratchet teeth. The lock plate also includes a lip extending at least partially around the beam bolt opening which captures the locking sleeve. The spring arm is movable between a first position where a lock plate detent is positioned in a spring arm notch which permits engagement of the ratchet teeth, and a second position where the side of the spring arm is in contact with the detent which disengages the ratchet teeth to permit loosening of the beam bolt.

Abstract: A repair apparatus for a shroud in a nuclear reactor pressure vessel is described. The repair apparatus includes an upper stabilizer assembly, a lower stabilizer assembly, and a tie rod configured to extend between and to couple to the upper and lower stabilizer assemblies. The upper stabilizer includes a stabilizer block and an upper stabilizer wedge slidably coupled to the upper stabilizer block. The upper stabilizer block is configured to couple to a shroud lug. The upper stabilizer wedge includes an integral leaf spring portion formed by a slot in the wedge and is configured to engage the side wall of the reactor pressure vessel. The lower stabilizer assembly includes a stabilizer block and a lower stabilizer wedge slidably coupled to the lower stabilizer block. The lower stabilizer block is configured to engage the shroud. A horizontal stabilizing spring is attached to the wedge and is configured to engage the side wall of the reactor pressure vessel. The tie rod is threaded at each end.

Abstract: Downcommer coupling apparatus and methods for replacing a core spray line downcommer pipe coupled to a shroud T-box are described. In one embodiment, the coupling apparatus includes a wedge flange, a wedge, a wedge housing, a pipe seal, a cylindrical pipe, an elbow, a lower flange, and a shroud seal. The downcommer pipe is connected to the coupling apparatus by extending the pipe through the wedge flange, the wedge, and the wedge housing. The wedge has a plurality of flexible thinned segments that extend into the wedge housing to secure the downcommer pipe to the wedge housing. Wedge flange bolts extend through the wedge flange, the wedge, and the wedge housing to rigidly secure the downcommer pipe to the coupling apparatus. Dowel bolts extend through the wedge housing and the downcommer pipe to provide vertical and torsional load transfer from the downcommer pipe to the coupling apparatus. The lower flange is configured to receive the shroud T-box.

Abstract: Apparatus for supporting the lower riser assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor. In one embodiment of the apparatus, the clamp assembly provides structural rigidity to the lower rise assembly. The clamp assembly includes a lower thermal sleeve clamp and a riser clamp. The lower thermal sleeve clamp is positioned adjacent an interface between the elbow and the thermal sleeve of the jet pump riser pipe assembly. The riser clamp is secured to the riser pipe of the jet pump riser pipe assembly at a location adjacent an interface between the riser pipe and the elbow. The lower thermal sleeve clamp and the riser clamp also are coupled to each other so that as the respective clamps are secured to the lower riser assembly.

Abstract: A method and an apparatus for stabilizing a shroud against lateral deflection. The shroud restraint stabilizer has springs which exert radially inwardly directed forces that resist lateral deflection of the shroud relative to the reactor pressure vessel. Each stabilizer includes a stabilizer preload spring and a seismic restraint spring. Each spring has resilient arms integrally connected to opposing ends of a common main support span. The resilient arms of the stabilizer preload spring form a first leaf spring of relatively lower stiffness and the resilient arms of the seismic restraint spring form a second leaf spring of relatively higher stiffness. The different stiffnesses are achieved by providing the first leaf spring with a longer base than that of the second leaf spring. The pads on the seismic restraint spring are in contact with the reactor pressure vessel, but are not preloaded under operating conditions. The seismic restraint spring is loaded in response to lateral deflection of the shroud, e.g.

Abstract: A method and an apparatus for inspecting a core shroud by remote operation. The apparatus is a robotic scanning device which can be installed in the narrow space between the core shroud and the jet pumps and which can scan azimuthally and vertically around the circumference of the core shroud. The scanning device provides gross positioning to the area of interest and precise motion control in a limited scanning range. The scanning uses a thin wide arm to support a bank of transducers at its bottom end, and is rigidly mounted to a precision two-axis positioner at its top end. The arm is of narrow thickness to pass through the 0.5-inch access opening and to allow radial flexibility to absorb surface contour variation over the inspection area. The transducer mounting includes a water jet thruster to provide a radially inwardly directed reaction force to maintain the transducers in contact against the shroud. The arm is fabricated with a row of longitudinal holes extending throughout its length.

Abstract: A method and an apparatus for restraining a cracked shroud against vertical joint separation. The method involves the placement of a plurality of tie rods (e.g., four) in the downcomer annulus at respective azimuthal positions, each of the tie rods having one end anchored to the shroud support plate. The other end of each tie rod is latched over the top edge of the shroud to counteract lifting forces exerted on the shroud by the bolts which hold down the shroud head.

Abstract: A welded bracket for use in repairing a shroud in which one or more shroud girth seam welds have experienced stress corrosion cracking. A plurality of the welded brackets are placed around the outer circumference of the shroud at a plurality of azimuthal positions at the elevation of the top guide support ring. Each bracket is constructed by welding curved plates. Welding productivity is increased by using an extremely thin weld joint design with a non-circular cylindrical, thin welding electrode having an elongated cross-sectional shape. During welding, the elongated dimension is aligned parallel with the length of the weld joint. This combination enables joining of the welded bracket parts with both the initial weld joint preparation and the completed weld having a uniquely thin width and with a high aspect ratio of depth to width. This high aspect ratio reduces the number of weld beads needed to build the weld joint.

Abstract: A method and an apparatus for repairing a shroud in which one or more shroud girth seam welds have experienced SCC. The method involves the placement of a plurality of brackets around the outer circumference of the shroud at a plurality of azimuthal positions. Each bracket has circular holes for receiving respective tapered pin assemblies. Corresponding circular holes are machined in the shroud wall at positions which will align with the holes in the bracket. Each tapered pin assembly is inserted and then manipulated remotely from outside the shroud. Each tapered pin assembly consists of three types of parts: a threaded tapered pin, a slotted sleeve with a tapered bore, and a threaded nut. When fully installed, the tapered pin is encased by the sleeve. As the tapered pin is tensioned, the sleeve exerts a radially outwardly directed contact pressure on the cylindrical surface of the aligned circular holes respectively formed in the bracket and shroud.

Abstract: An apparatus for stabilizing a core plate against lateral deflection. A plurality of core plate wedge assemblies (e.g., four) are installed in the circumferential gap between the circular outer peripheral edge of the core plate and the circular cylindrical wall of the middle shell of the shroud at respective azimuthal positions. These core plate wedge assemblies are wedged into place with preload to maintain the spacing between the core plate and the shroud, thereby maintaining the alignment of the fuel assemblies. The core plate wedge assemblies further serve to transmit loads from the nuclear fuel core to the core shroud at azimuthal locations where lateral shroud restraints outside the shroud contact the reactor pressure vessel.

Abstract: A lock fastener includes a tubular collar having a plurality of protuberances extending radially inwardly from an inner surface thereof and adapted for cooperating with a bolt to retain the collar thereon. A lock ring surrounds an outer surface of the collar and has an initial inner diameter. The lock ring is formed of shape memory metal alloy effective for shrinking the lock ring to a final inner diameter less than the initial inner diameter upon change in temperature thereof to in turn shrink the collar for clamping the protuberances in locking contact with the bolt.

Abstract: A fastener includes an annular body having a screw thread spiraling therearound. The thread has a crest and a pair of front and back flanks extending laterally therefrom, with a start end disposed adjacent to a front end of the body. The start end is flat from the back flank to the front flank and is inclined at an acute back angle relative to a helical axis of the crest for facing the start end toward a back end of the body.

Abstract: An apparatus and method are provided for servicing an irradiated nuclear control rod underwater in a reactor building servicing pool. A turntable containing a plurality of spaced apart tools is positioned adjacent to the control rod. A first tool aligns the turntable relative to the radioactive roller mounted to the control rod by a radioactive pin therethrough. The turntable is indexable to position a second tool adjacent to the radioactive roller and pin, with the second tool being effective for freeing the radioactive pin from the control rod. The turntable is indexable for positioning a third tool adjacent to the radioactive roller and pin for removing the radioactive pin and the roller from the control rod. In further embodiments of the invention the turntable is further indexable for positioning a fourth tool adjacent to the control rod for reaming the pin aperture through which the radioactive pin was mounted.

Abstract: In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, a method for the submerged welding repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. An alignment device registers to a hole in the core plate and its corresponding guide pin. A control rod drive housing mating fixture on the depending extremity of the shaft of the alignment device precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand. For the welding repair process herein, a welding cylinder apparatus fits over the depending end of the shaft of the alignment device.

Abstract: In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, an apparatus and method for the submerged welding repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. The apparatus registers to a hole in the core plate and its corresponding guide pin. A mating fixture on the depending extremity of the shaft of the apparatus precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand. For the welding repair process herein, a welding cylinder apparatus fits over the depending end of the shaft of the alignment device.

Abstract: In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, an apparatus for the repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. The apparatus registers to a hole in the core plate and its corresponding guide pin. A mating fixture on the depending extremity of the shaft of the apparatus precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand.

Abstract: In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, an apparatus and method for the repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. The apparatus registers to a hole in the core plate and its corresponding guide pin. A mating fixture on the depending extremity of the shaft of the apparatus precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand.

Abstract: In a light water reactor system using the thorium-232 -- uranium-233 fuel system in a seed-blanket modular core configuration having the modules arranged in a symmetrical array surrounded by a reflector blanket region, the seed regions are disposed for a longitudinal movement between the fixed or stationary blanket region which surrounds each seed region. Control of the reactor is obtained by moving the inner seed region thus changing the geometry of the reactor, and thereby changing the leakage of neutrons from the relatively small seed region into the blanket region.