Abstract: An ultrasonic waveguide includes a fluid-tight thin-walled tube filled with a viscous, compressible fluid. One end of the tube is coupled to a transducer for transforming electrical energy into waves of ultrasonic energy which propagate the length of the tube. The other end of the tube has a window or refracting "shoe" for transmitting or refracting the propagating ultrasonic wave therethrough. The tube has a substantially constant cross section, preferably circular. The internal diameter of the preferred circular tube is in the millimeter regime, preferably from 0.25 to 1 mm. The wall material is preferably metal, plastic or metal/plastic composite.

Abstract: An internal passive catalytic device operating in the water phase of a boiling water reactor vessel downstream of the steam/water separator location. The device consists of catalytic material arranged and situated such that all (except perhaps a small leakage flow) water phase exiting the water/steam separator device flows over the surface of the catalytic material. The catalytic surfaces decompose dissolved hydrogen peroxide into water and oxygen. When the substrate of the catalytic material is plated or alloyed with a water recombination catalyst such as a noble metal, the catalytic surfaces also catalyze the recombination of dissolved hydrogen and oxygen molecules into water. The passive catalytic device is constructed to ensure that the pressure drop of the reactor water across the device is very small.

Abstract: A passive decomposer operating in the water/steam mixture exiting the core of a boiling water reactor. The decomposer comprises a catalytic material arranged and situated such that substantially all of the water/steam mixture entering the water/steam separator device flows over the surface of the catalytic material. The catalytic decomposing surfaces decompose hydrogen peroxide molecules dissolved in the liquid phase to form water and oxygen molecules. The passive catalytic decomposer is constructed to ensure that the pressure drop of the reactor water across the device is very small. The decomposer can include a plurality of stainless steel flow-through housings packed with stainless steel catalytic decomposer material, which could take the form of tangled wire or strips, crimped ribbon, porous sintered metal composite or any other structure having a high surface area-to-volume ratio.

Abstract: A composite nuclear fuel container for service in water cooled nuclear fission reactor plants having improved resistance to corrosion, and a method of producing same. The invention comprises each component of the fuel container being of specific compositions which have been heat treated to transform their microcrystalline structure in such a manner to optimize the corrosion resistance of each component of the fuel container.

Abstract: A latch assembly removably joins a steam separator assembly to a support flange disposed at a top end of a tubular shroud in a nuclear reactor pressure vessel. The assembly includes an annular head having a central portion for supporting the steam separator assembly thereon, and an annular head flange extending around a perimeter thereof for supporting the head to the support flange. A plurality of latches are circumferentially spaced apart around the head flange with each latch having a top end, a latch hook at a bottom end thereof, and a pivot support disposed at an intermediate portion therebetween and pivotally joined to the head flange. The latches are pivoted about the pivot supports for selectively engaging and disengaging the latch hooks with the support flange for fixedly joining the head to the shroud or for allowing removal thereof.

Abstract: A passive containment cooling system includes a containment vessel surrounding a reactor pressure vessel and defining a drywell therein containing a non-condensable gas. An enclosed wetwell pool is disposed inside the containment vessel, and a gravity driven cooling system (GDCS) pool is disposed above the wetwell pool in the containment vessel and is vented to the drywell. An isolation pool is disposed above the GDCS pool and includes an isolation condenser therein. The condenser has an inlet line disposed in flow communication with the drywell for receiving the non-condensable gas along with any steam released therein following a loss-of-coolant accident (LOCA). The condenser also has an outlet line disposed in flow communication with the drywell for returning to the drywell both liquid condensate produced upon cooling of the steam and the non-condensable gas for reducing pressure within the containment vessel following the LOCA.

Abstract: A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell.

Abstract: An improved emergency cooling system and method is disclosed that may be adapted for incorporation into or use with a nuclear BWR wherein a reactor pressure vessel (RPV) containing a nuclear core and a heat transfer fluid for circulation in a heat transfer relationship with the core is housed within an annular sealed drywell and is fluid communicable therewith for passage thereto in an emergency situation the heat transfer fluid in a gaseous phase and any noncondensibles present in the RPV, an annular sealed wetwell houses the drywell, and a pressure suppression pool of liquid is disposed in the wetwell and is connected to the drywell by submerged vents. The improved emergency cooling system and method has a containment condenser for receiving condensible heat transfer fluid in a gaseous phase and noncondensibles for condensing at least a portion of the heat transfer fluid.

Abstract: An improved method for repair of incore-instrumentation-housing and related defects in a nuclear reactor system involves three stages, each with ultrasonically assisted inspections. In the first stage, a defective incore housing is removed and the exposed area and aperture at the former location of the incore housing is ultrasonically inspected using an ultrasonic probe with a tiltable disk-shaped head that self-conforms to the local contour of the reactor vessel bottom. In the second stage, a weld buildup is formed. The reactor is then sealed and the weld buildup is machined to define an aperture therethrough. The weld buildup is then ultrasonically inspected with a second probe with a centering member that is stationary as the probe body is moved vertically relative to it. In the third stage, a J-prep is formed. A new incore housing is inserted through the weld buildup aperture. The new incore housing is welded at the J-prep. The J-weld is ultrasonically inspected using a third ultrasonic probe.

Abstract: In combination with a boiling water nuclear reactor core undergoing a reload, an improved core reload and process of reloading is disclosed. The core reload consists of fuel bundles having differing design margins to critical power and linear heat generation rate. Specifically, a first part of the core reload is selected from fuel bundles having relatively high critical power margin and relatively lower linear heat generation margin. A second part of the core reload is selected from fuel bundles having relatively high linear heat generation margin and relatively low critical power margin. Distribution of the reload fuel bundles throughout the reactor core occurs as a function of critical power margin and linear heat generation rate margin. Specifically, fuel bundles having the high critical power margin are placed in selected intervals to the central portion of the cylindrical core. Fuel bundles having high linear heat generation margin are placed in the peripheral region of the core.

Abstract: An especially designed probe carries preferably five transducers for the examination of a right circular cylinder flooded with water having limited vertical clearance from the point of required non destructive inspection. The probe includes a generally disc shaped body having a minimal vertical dimension and a radius slightly less than the radius of the right circular cylinder to be inspected. Insertion of the probe interior of the right circular cylinder occurs. At the periphery of the disc, there are disposed five interrogating acoustical transducers. These transducers are spaced from preselected staggered circumferential locations with respect to the right circular cylinder for examination of the water flooded cylinder with refracted rays.

Abstract: A natural circulation boiling water reactor system comprises a reactor vessel enclosing a reactor core, for generating steam to drive a turbine which can drive a generator to generate electricity. The vessel includes a chimney for guiding the recirculating water and steam vertically above the core and a dryer for helping to remove water from steam exiting the vessel toward the turbine. In contrast to prior reactor systems, the chimney is height-staggered so that its central sections are taller than its peripheral sections. Likewise, a dryer is elevation-staggered. This staggering minimizes carryover, water in the steam flow to the turbine, and carryunder, steam in the water recirculating through the core. In addition, the staggered chimney causes the fastest recirculation flow through the hottest portions of the core. The overall effect is a more efficient reactor system.

Abstract: A nuclear reactor is joined to a steam turbine by a main steamline for discharging steam thereto. A plurality of flow control valves regulate flow to the turbine, and a bypass valve selectively bypasses a portion of the steam around the turbine to its condenser. A pressure regulator and turbine controller are operatively joined to the control valves and the bypass valve for controlling steamflow to the turbine. An apparatus for detecting failure of one of the control valves is operatively connected to the bypass valve, and upon failure of one of the control valves to channel sufficient flowrate, the bypass valve is automatically opened to reduce reactor pressure rise. The failure detecting apparatus also provides a reduction demand signal for reducing reactor power for allowing the bypass valve to close.

Abstract: A captive fastener is joinable to a stud for being retained in a nuclear reactor. The fastener includes a head fixedly joinable to the stud, and at least one spring clip extending perpendicularly from the head and having a proximal end fixedly joined thereto, and a distal end in the form of hook for retaining the fastener in the reactor. The hook is resiliently deflectable laterally relative to the head for allowing assembly and disassembly.

Abstract: One aspect of the present invention comprises an apparatus for storing an end effector nestably adjacent a pipe to which it is attached and for moving the end effector into a working position laterally-displaced from said pipe is disclosed. Such apparatus desirably is part of the robotic welding apparatus wherein the end effector is a welding head. This apparatus comprises a pair of pipe segments in rotating end-abuttable relationship, each segment bearing a ring gear about its circumference; a pair of helical lotus petals having an in inner surface which conforms to the outer surface of the pipe segment to which each lotus petal is hingedly attached at its distal end, each lotus petal being attached hingedly at their respective distal ends to a lotus petal hinge attachment stage; drive means drivably connected to each of said ring gears for separately driving each pipe segment; and an end effector carried by said lotus petal hinge attachment stage.

Abstract: A nuclear fuel pellet loading system includes pellet handling apparatus and cladding tube handling apparatus functionally interfaced by a bushing assembly. Pellet rows of varying zone lengths are alternately built up on two tracks, measured for zone length, weighed and then loaded by separate pusher carriages through separate bushing assembly passageways into a pair of empty cladding tubes indexed into loading positions by the tube handling apparatus. Separate zone interface tapes affixed to the pusher carriages indicate to an operator the length each pellet zone is to be built to. The tube handling apparatus accommodates cladding tubes of varying lengths and is equipped to automatically read a serial number imprinted on each tube endplug.

Abstract: A spacer pad for a nuclear control rod includes first and second halves each including a head and a shank. The shanks are configured for joining together the pad first and second halves, and the shanks are independently locked together for preventing the disassembly thereof. In an exemplary embodiment, the first and second shanks are threadingly joined together, and then independently locked together using a complementary hook and ledge respectively supported by the pad halves which allows assembly together of the pad halves but prevents disassembly thereof.

Abstract: An assembly for servicing a cruciform control blade includes a carriage having first and second crossarms each containing a generally U-shaped slot for receiving the top of the control blade. The first crossarm includes a clamping actuator to rigidly clamp the carriage to the blade top. The second crossarm includes a tool positionable adjacent to a roller aperture in a selected one of the four panels of the control blade. The tool is positioned on the second crossarm at a predetermined depth, and at a predetermined lateral span from the first crossarm so that upon mounting of the carriage on the blade top and actuation of the clamping actuator, the tool is vertically and laterally aligned with a center of the panel roller aperture. In one embodiment, the tool is effective to sever the roller from the panel aperture without damaging the panel, and in another embodiment the tool is effective for installing a replacement spacer pad in the aperture.

Abstract: A method for chemically controlling cobalt decontaminating the water cooling system of a water cooled nuclear fission reactor to reduce the radiation hazard to personnel.

Abstract: Part length water regions are located above part length fuel rods in boiling water nuclear reactor fuel bundles. The part length water regions include discrete containers having entry ports at the top of the part length water regions for capturing water, and vent ports for permitting internally generated steam to escape. The advantages of improved neutron moderation in the upper portion of the fuel assembly are maintained while the uranium fuel removal requirements are minimized.