Abstract: A tool for installing a support member which must be rotated into a horizontal position in the downcomer annulus of a boiling water reactor by remote manipulation. The support member may, for example, be a midsupport for damping flow-induced vibrations in a vertical restraint tie rod. The tool includes a rigid holder for holding the support member and a threaded pivot for coupling with the threaded end of a cable. The pivot can swing relative to the holder between first and second angular positions separated by 90.degree.. The support member is held in the holder by a pair of channels formed on the holder and a set screw which threads in the holder and enters a bore formed in the support member. After the support member has been secured to the holder, the holder is coupled to the end of the cable via the pivot. The support member is lowered in the downcomer annulus in a vertical position.

Abstract: An unlatching tool which can be used to uncouple and grapple standard handle and extended handle control rods from their associated control rod drives. The unlatching tool is lowered onto the handle of a control rod residing in the reactor core. Due to differences in the shapes of the handles of the standard handle and extended handle control rods, the tool is able to sense the type of control rod present and, through the use of a pneumatically actuated cylinder, position the unlatching mechanism at the appropriate elevation. In particular, a four-way valve, that is actuated by contact with the top corner of the handle of the extended handle control rod and is not contacted by the handle of the standard handle control rod, is used to differentiate between control rod types. The unlatching mechanism is positioned relative to the unlocking handle on the control rod using a pneumatic cylinder activated by the four-way valve.

Abstract: A tool for radially positioning a hoisted load suspended from the refueling bridge by a cable and facilitating lowering of the hoisted load into the downcomer annulus of a boiling water reactor. During repair of the shroud, hardware must be lowered into the annulus for installation. The hardware installation in turn requires the lowering of tooling into the annulus and its subsequent removal via cables. The feedwater sparger and core spray piping are located above and partially obstruct the vertical access to the annulus. To protect the feedwater sparger and core spray piping against damage during the lowering of various hardware and tooling into the annulus, a cover is installed over the feedwater sparger and core spray piping at the azimuthal location of the hoist. This cover further limits the vertical access to the annulus. A steam dam slide with a cable manipulator is seated on the shroud flange at the azimuthal location of the repair procedure.

Abstract: A system for suppressing the pressure inside the containment of a BWR following a postulated accident. A piping subsystem is provided which features a main process pipe that communicates the wetwell airspace to a connection point downstream of the guard charcoal bed in an offgas system and upstream of the main bank of delay charcoal beds which give extensive holdup to offgases. The main process pipe is fitted with both inboard and outboard containment isolation valves. Also incorporated in the main process pipe is a low-differential-pressure rupture disk which prevents any gas outflow in this piping whatsoever until or unless rupture occurs by virtue of pressure inside this main process pipe on the wetwell airspace side of the disk exceeding the design opening (rupture) pressure differential. The charcoal holds up the radioactive species in the noncondensable gas from the wetwell plenum by adsorption, allowing time for radioactive decay before the gas is vented to the environs.

Abstract: A stand-alone low-voltage direct current power supply, for use as a battery, which is energized by the decay of a radioactive isotope in response to neutron capture. During this decay, either .alpha.- or .beta.-particles are emitted. The emitting radioactive isotope should have adequate half-life and no .gamma.-emission. The preferred .beta.-emitting radioisotope is thallium, which decays directly to the ground state of Pb.sup.204 by 763-keV .beta.-decay with no .gamma.-emission. The resulting .beta.-particles are collected to form a current which can be used for various purposes inside a reactor. The preferred .alpha.-emitting radioisotope is americium.

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 self-aligning seal system for facilitating the repair or replacement of components of recirculation pump assemblies which penetrate the bottom head of the reactor pressure vessel of a boiling water reactor. The self-aligning seal system enables an operator to block off stub openings in the bottom portion of a water-filled reactor pressure vessel while performing maintenance in an underlying dry field without draining the coolant water from the reactor pressure vessel. To prevent leakage due to misalignment of the seal relative to the open end of the stub, the seal system is provided with a self-alignment guide member which centers the sealing unit relative to a diffuser opening coaxial with the stub as the sealing unit is lowered onto the stub.

Abstract: A reactor protection system having four divisions, with quad redundant sensors for each scram parameter providing input to four independent microprocessor-based electronic chassis. Each electronic chassis acquires the scram parameter data from its own sensor, digitizes the information, and then transmits the sensor reading to the other three electronic chassis via optical fibers. To increase system availability and reduce false scrams, the reactor protection system employs two levels of voting on a need for reactor scram. The electronic chassis perform software divisional data processing, vote 2/3 with spare based upon information from all four sensors, and send the divisional scram signals to the hardware logic panel, which performs a 2/4 division vote on whether or not to initiate a reactor scram. Each chassis makes a divisional scram decision based on data from all sensors.

Abstract: A vapor of diethylzinc or dimethylzinc is reacted with water vapor to form very small particles of depleted zinc oxide which are entrained in the gas flow. In accordance with one version of the method, a spray nozzle is used to mix liquid diethylzinc with dry nitrogen to prevent combustion. The nozzle sprays the diluted diethylzinc into a chamber heated up to its boiling point of 118.degree. C. to completely vaporize the diethylzinc. The diluted diethylzinc gas is then reacted with water vapor to form a fume of very small zinc oxide particles entrained in ethane gas without combustion. A similar process can be used to convert dimethylzinc into depleted zinc oxide powder. In accordance with another version of the process, an inert gas stream is saturated with diethylzinc or dimethylzinc vapor by passing a dry inert gas through a vessel containing liquid diethylzinc or dimethylzinc. A second inert gas stream is saturated with water vapor in a similar manner.

Abstract: A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.

Abstract: A method and an apparatus for electrically suppressing electrochemical potential near highly susceptible components of a boiling water reactor. A small self-powered, electrical device is affixed to the metal area to be protected, which device has the capacity to locally suppress electrochemical potential automatically and continuously without provision for external power supplies, cables, penetrations, or other paraphernalia usually associated with electrical and electronic systems. The result is that components susceptible to intergranular stress corrosion cracking are not as sensitive to the details of the water chemistry flowing over them and do not crack as much, or as rapidly, as presently. The new technique is based on the concept of supplying electrons directly and locally to the sensitized zone(s) of the metal, thereby inhibiting intergranular stress corrosion cracking. The source of the electrons is .beta.-emitting material which is contained in a housing attached to the metal.

Abstract: A nuclear reactor having a pressure vessel which is open at the top. The open top of the pressure vessel is closed by a steel dome. A containment, which is open at the top, extends upward from and is joined to the top of the pressure vessel and has an open containment head at the top thereof. The open top of the containment is closed by a steel dome, thereby forming a containment well bounded laterally by the containment, on the bottom by the vessel closure and on the top by the containment closure. The pressure vessel can be a steel-lined prestressed concrete vessel, while the containment is formed by an extension of the prestressed concrete vessel. Alternatively, the pressure vessel and the containment are parts of a unitary steel vessel. Isolation valves are installed on each penetration pipeline to isolate the system in the event of a loss-of-coolant accident.

Abstract: An apparatus for removing and installing a reactor component, such as a circulating pump, by remote operation. The apparatus includes a handling mechanism for transporting various interchangeable containers and tools along a path between a position on top of the suppression pool and a position overlying the reactor component. The handling mechanism has a yoke assembly adapted to receive and support the trunnions of any container or tool, lifting screws for raising and lowering the yoke assembly and an arcuate rack mounted on the shield wall for rotating the yoke assembly around the circumference of the shield wall. A transition collar is latched onto the pump pressure housing. The transition collar has a valve at the top for closing off its interior. Seals arranged between the transition collar and pressure housing to ensure water-tightness.

Abstract: An electrode probe for measuring the electrochemical potential of a surface at a location of interest in a boiling water reactor. The probe has a monolithic sensor configuration built into a single stainless steel mineral insulated (MI) cable. This monolithic sensor can be used as a switch to detect when the appropriate concentration of dissolved hydrogen required to provide IGSCC mitigation is present at any location inside the reactor. Using the sensor switch, it is possible to in situ instantly determine the minimum hydrogen level required to reach the IGSCC protection potential. The sensor configuration consists of a metal/metal oxide/ZrO.sub.2 sensor and a noble metal sensor in a combination wherein the outer sheath of a mineral insulated cable acts as the conductor for the noble metal and the central conductor of the MI cable acts as the conductor for the metal/metal oxide/ZrO.sub.2. The metal/metal oxide/ZrO.sub.2 sensor acts as a reference electrode in the BWR environment (i.e.

Abstract: An improved containment configuration for a boiling water reactor in which the wetwell airspace is divided into a multiplicity of chambers through the use of wetwell airspace divider partitions. The partitions extend to below the water level of the suppression pool so that the gas in one airspace chamber cannot communicate with another airspace chamber. Each wetwell airspace chamber can be placed in flow communication with the drywell via a respective open vacuum breaker. When one vacuum breaker fails in the open position or when wetwell/drywell steam bypass leakage into one chamber occurs, the pressure differential between the wetwell airspace chamber and the drywell drops. However, because the leaking chamber is isolated, the pressure differential between the drywell and the other chambers is unaffected. Thus, the PCC heat exchangers corresponding to non-leaking chambers can continue to operate effectively, even if the PCC heat exchanger corresponding to the leaking chamber is rendered ineffective.

Abstract: A method and an apparatus for in situ ultrasonic inspection of the core spray T-box to thermal sleeve attachment weld and the core spray T-box to cover plate attachment weld in BWRs. The apparatus incorporates a stationary clamping mechanism and sliding and rotational mechanisms which are operated remotely to scan the transducer over the T-box welds and heat-affected zones thereof.

Abstract: A linear actuator for actuating a valve or other control element. The actuator measures the in-line or axial force exerted on a drive sleeve after the valve disk engages the valve seat or back seat In response to detection of an axial force in excess of a predetermined threshold level, the motor is de-energized. The linear actuator includes a drive sleeve rotatably supported by bearings; a pack of friction springs for axially supporting the drive sleeve; a drive motor for driving rotation of the drive sleeve by way of gearing; a ball screw nut coupled inside and coaxial with the drive sleeve such that the ball screw nut rotates with the drive sleeve; a ball screw which translates axially in response to rotation of the ball screw nut; an anti-rotation device for preventing rotation of the ball screw during its translation; a switch for controlling the ON-OFF state of the motor; and a mechanical assembly for actuating the switch in response to a predetermined amount of axial deflection of the drive sleeve.

Abstract: A tool which can be remotely operated to precisely measure the downcomer annulus width at the elevation of the top guide support ring. The measuring tool has a support frame adapted to be grappled and then hooked onto the upper rim of the shroud, and a measuring subassembly mounted on the support frame. The measuring subassembly has a contact block mounted on a bearing-mounted slider. The slider is translatable between a retracted (i.e., "home") position and an extended position in response to actuation of a cylinder mounted on the support frame. When the tool is properly installed on the rim of the shroud, the slider travels radially outward in response to actuation of the cylinder until the contact block abuts the opposing inner surface of the reactor pressure vessel wall, i.e., the slider is stopped.

Abstract: The surfaces of a metal or alloy component are scrubbed by a high-velocity stream of inert gas at temperatures which facilitate removal of contaminants. Simultaneous with scrubbing, the impurities are captured in a separated loop of one or more "getter" filters operating at optimized temperatures. The scrubbing and "getting" functions are followed by a rapid elevation of the temperature of the component by heating the inert gas, now essentially free of contaminants which would otherwise react with the component surface at the elevated temperatures. Thereafter, a specific protective layer-forming agent is introduced into the inert gas stream at an ideal temperature, which agent will react predictably with the component being treated to form a predetermined protective coating on its surface.

Abstract: A process and a system for detecting defective nuclear fuel assemblies in situ. The system includes two basic subsystems. The first subsystem is a sample collection system consisting of a hood placed over the fuel. A technique whereby a vacuum is drawn across a submerged nozzle of a degas tank is used to draw up the sample of fluid out of a fuel assembly. The second subsystem determines the amount of Kr-85 radioisotope contained in the fluid sample. This information is used to determine whether the fuel assembly contains a defective, i.e., leaking, fuel rod. The measurement values for Kr-85 in the fluid sample extracted from the fuel assembly are compared to the measurement values for Kr-85 in fluid samples taken from the reactor pool prior to fuel assembly testing and fluid samples taken from non-leaking control cells, the latter values representing the background to which the subject fuel assembly is compared.