Abstract: A system for improving the performance of nuclear power plant feedwater control systems and simplifying steam generator low water level reactor protection logic includes a plurality of water level channels for measuring steam generator water level and generating a plurality of signals representative thereof. The median steam generator water level signal is selected from among the plurality of steam generator water level signals. The median steam generator water level signal is then communicated to the feedwater control system through an output interface.

Abstract: A passive safety injection system relies on differences in water density to induce natural circulatory flow patterns which help maintain prescribed concentrations of boric acid in borated water, and prevents boron from accumulating in the reactor vessel and possibly preventing heat transfer.

Abstract: The movable air baffle shield means in accordance with the present invention provides an efficient method of cooling the space surrounding the containment vessel while also providing the capability of being moved away from the containment vessel during inspection. The containment apparatus comprises a generally cylindrical sealed containment vessel for containing at least a portion of a nuclear power generation plant, a disparate shield building surrounding and housing the containment vessel therein and spaced outwardly thereof so as to form an air annulus in the space between the shield building and the containment vessel, a shield baffle means positioned in the air annulus around at least a portion of the sides of the containment vessel providing a coolant path between the baffle means and the containment vessel to permit cooling of the containment vessel by air, the shield baffle means being movable to afford access to the containment vessel.

Abstract: A linear programming matrix is used to represent a complex process with many interrelated process variables. Assumptions are initially made regarding the values of the matrix elements, based on current or expected operation of the process. After the linear programming matrix is solved, the values of the coefficients are modified according to a test strategy and the linear programming matrix is again solved in an effort to obtain a better result. This process is repeated until solutions of matrix converge and the amount of modification of the matrix is minimal. One test strategy that can be used is SIMPLEX self-directing evolutionary operation. Another test strategy uses progressively more accurate linear approximations of nonlinear relationships in the linear programming matrix.

Abstract: A motor-generator set, which has a rotatable central shaft, AC and DC rotors tandemly-arranged along the shaft for rotation therewith and a liquid coolant flow path defined through the shaft and rotors, includes rotating unions mounted internally of the shaft within first and second axial bores defined in opposite ends thereof. Liquid coolant enters the axial bore at one end of the shaft and exits the axial bore at the opposite end of the shaft via the internally-located rotating unions. The rotating unions each includes features for collecting leakage of residual amounts of fluid from the bores past the unions, and fluid transmission coupling features being mounted respectively to the rotating unions for attachment to transmission lines for supplying and discharging fluid to and from the unions.

Abstract: This invention is for the processing of a somewhat broader range of compositions, including ZIRLO material. It controls creep rate in an alloy having, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.28 of at least one of iron, nickel and chromium and up to 220 ppm carbon, and the balance essentially zirconium. The method is of a type which utilizes subjecting the material to a post extrusion anneal, a series of intermediate area reductions and intermediate recrystallization anneals, with one of the intermediate recrystallization anneals possibly being a late stage beta-quench, a final pass area reduction, and a final stress relief anneal.

Abstract: A method and apparatus for monitoring the velocity of flow of a fluid, by: causing fluid to flow through a conduit section defining a monitoring region, the conduit section having an interior defining a flow path which is free of any physical obstruction that can significantly influence fluid flow in the monitoring region; propagating a beam of energy across the flow path in the monitoring region in a direction transverse to the flow path, the energy being selected such that the beam is modulated by turbulence occurring in the fluid; detecting the modulated beam at a single location in the monitoring region after the beam has traversed the flow path and generating a single electrical signal representative of the detected modulated beam; and processing the single electrical signal in a manner to provide an indication of the modulation of the beam produced by the turbulence in the fluid.

Abstract: An annealing apparatus is described which is designed, manufactured, preassembled and tested at a factory in equal-sized, longitudinal, self-contained segments. In a typical arrangement each segment is one-quarter of the total unit. Each segment includes a support frame, an arcuate heater shell covered with a plurality of heaters and thermocouples, heater and thermocouple connectors, a segmented upper flange, a utility flange and connectors for attaching adjacent segments. Each segment is transported to the nuclear reactor, fit through the equipment hatch of the containment building and assembled in the reactor vessel with the remaining segments using a crane in the building. Appropriate connections for the individual heaters and thermocouples of each segment are made by personnel introduced into the building and are led out the top of the annealing apparatus to a control station.

Abstract: This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200.degree.-1300.degree. F., and to a beta quench two steps prior to final size.

Abstract: A reactive metal such as zirconium, hafnium, and titanium is subjected to comminution in a closed chamber containing a non-reactive gas modified by the addition of an amount of a vaporized liquid hydrocarbon.

Abstract: An apparatus for monitoring the pressure within a cask containing radioactive materials is disclosed. The apparatus comprises a differential pressure sensor sealingly connected to a bore that penetrates through the wall of the cask for directly monitoring the pressure of the helium gas contained within the cask and for providing a first barrier between the helium gas and the ambient atmosphere. An evacuated sensor chamber surrounds both the outlet end of the through-wall bore and the differential pressure sensor for providing a second barrier between the helium and the ambient atmosphere as well as a vacuum reference point for the differential pressure sensor. An absolute pressure sensor is connected in parallel to the through-wall bore to allow the system operator to determine whether or not a reduction in the pressure sensed by the differential pressure sensor is the result of a leakage condition in the cask, or in the evacuated sensor chamber.

Abstract: A preferred embodiment of the present invention provides an incore instrumentation system for detecting conditions, e.g., neutron flux density, within the core of a pressurized water nuclear reactor (PWR). The instrumentation system includes a plurality of long straight thimbles (52), containing fixed incore detectors, which are inserted through the top closure head (18) of the PWR. The invention meets today's principal utility, EPRI, DOE and NRC requirements and preferences, including no bottom RV head penetrations and the use of fixed incore instrumentation. In addition, an instrumentation system according to the invention is mechanically simple with a straight core insertion/removal path that does not conflict with or add significant complexity to the reactor internals.

Abstract: An acoustical wave trap is combined with the rupture disc or relief valve used in vessels for storing potentially explosive materials. The acoustical wave trap operates to substantially reduce the magnitude of the rarefaction wave produced within the vessel when the rupture disc or relief valve opens, and thereby simplifies the pressure relief requirements.

Abstract: An apparatus is provided for determining the thermal history of an environment for purposes of monitoring thermal aging in equipment or the extent to which a process has proceeded. The apparatus comprises a plurality of solid state track recorders, and the range of activation energy values among the solid state track recorders encompasses the activation energy of the thermal aging process of the equipment to be monitored. Using Arrhenius functions, data obtained from the apparatus can be used to determine an equivalent average temperature which is combined with the equipment life data to determine the extent of thermal aging.

Abstract: Hybrid nuclear reactor grey rods are described, wherein geometric combinations of relatively weak neutron absorber materials such as stainless steel, zirconium or INCONEL, and relatively strong neutron absorber materials, such as hafnium, silver-indium cadmium and boron carbide, are used to obtain the reactivity worths required to reach zero boron change load follow. One embodiment includes a grey rod which has combinations of weak and strong neutron absorber pellets in a stainless steel cladding. The respective pellets can be of differing heights. A second embodiment includes a grey rod with a relatively thick stainless steel cladding receiving relatively strong neutron absorber pellets only. A third embodiment includes annular relatively weak netron absorber pellets with a smaller diameter pellet of relatively strong absorber material contained within the aperture of each relatively weak absorber pellet.

Abstract: A process for extracting scandium from titanium ore includes the steps of: feeding the titanium ore to a fluidized bed chlorinator at about 1000.degree. C. to produce a vaporous (generally titanium and possible iron chlorides) phase and a scandium-containing residue; and recovering the scandium from the residue.In one practice, the scandium is recovered by leaching the residue with aqueous acid (e.g. HCl) to produce a scandium-containing aqueous solution, followed by contacting the aqueous solution with a polyalkyl phosphate-containing organic phase, the polyalkyl phosphate (e.g. tributyl phosphate) extracting scandium into the organic phase, followed by scandium precipitation by an ammonium addition to produce a scandium hydroxide precipitate and the scandium hydroxide is calcined, whereby scandium is recovered as an oxide. The residue generally also contains yttrium and lanthanides, and the yttrium and lanthanides can also be recovered from the residue as a part of the scandium recovery process.

Abstract: This is a process for extracting scandium from zircon ore. It utilizes feeding zircon sand to a fluidized bed chlorinator at about 1000.degree. C. to produce a vaporous (principally zirconium and silicon chlorides) phase and a solid residue and recovering scandium from the solid residue. Surprisingly, despite the relatively low sublimation temperature of scandium chloride the very low level of scandium present in zircon ore is concentrated in the residue (rather than going with the vapor phase, where it would not be concentrated), making recovery of scandium from the zircon ore economically feasible. Generally, the process can be part of the production of zirconium metal, whereby scandium is a byproduct of zirconium production. Preferably, the recovery is performed by leaching the residue with aqueous acid (e.g. HCl) to produce a scandium-containing aqueous solution, followed by contacting the aqueous solution with a polyalkyl phosphate-containing organic phase, the polyalkyl phosphate (e.g.

Abstract: The present invention is a system that updates a pressurized water reactor core model, or data file describing the core, periodically using measured values determinable from core instrumentation. The system starts with a calibrated model calibrated from a flux map and a boron concentration measurement both determined monthly. Reactor system measurements are performed and the model is updated from the measurements using a standard depletion calculation. Some of the measured values are also used to determine measured actual values of axial offset and pinch. Standard neutronics equations are used to calculate analytical values of axial offset and pinch from the model, and the measured and calculated values are compared. If a deviation beyond a certain magnitude is detected, buckling coefficients in the model are adjusted to compensate for model drift. The updated model is stored and a time-out period is entered until it is time for another drift compensation cycle to start.

Abstract: A method and machine adapted to deburr items having burrs, particularly pressed sponge metal compacts of zirconium or hafnium. The burrs are gently scraped away by one or more endlessly moving, substantially horizontal preferably rotary screens preferably of stainless steel wire, which carry the items to be deburred. An item-confining wall and a series of baffles are associated with each screen for guiding the items back and forth across the upper surface of the screen and for passing the items through a passageway in the confining wall. The shavings of deburred material drop through the screen and are collected below. Means, such as item turning chutes, are provided between screens so that opposite sides of an item to be deburred, such as a washer-shaped item having flat opposite sides, will be completely deburred in a single pass through the machine.

Abstract: A superconductive alloy of titanium and niobium is formed during reduction of niobium pentoxide by adding an effective quantity of titanium metal and/or titanium oxide to a reduction mixture of aluminum and niobium pentoxide. The resulting mixture is reacted to form the desired niobium titanium alloy below an aluminum oxide or aluminum oxide-titanium oxide slag. The slag is easily separated from the alloy.