Abstract:
Prioritization logic determines the final commmand applied to a process control component (3) from a plurality of commands generated by diverse independent control subsystems (5A, 5B, 5N), each utilizing different hardware and software to implement a common algorithm to preclude common mode failures. In one embodiment, priority is given to commands generated by one control subsystem, such as a safety grade subsystem, over commands provided by a second, non-safety grade control subsystem. In another embodiment, equal priority is given to commands from two control subsystems. In this case, ambiguous commands from either or both subsystems are ignored, but conflicting commands produce a final command which provides a safe state.
Abstract:
A variable area restrictor is disclosed that is preferably used in a turbine engine to provide improved matching between the pressure required for aerofoil cooling and the somewhat lower pressure requirement for supplying air to the interstage seals and disc cavities. In a preferred embodiment, the valve of the present invention comprises a spring loaded valve assembly with a fixed minimum flow area controlled by pre-setting a minimum dimension for the opening between an inlet and the housing or body of the valve. A pre-loaded spring maintains the lift at this minimum dimension until the pressure drop across the flow area exceeds a certain value. Above this critical pressure drop, the valve lifts, causing the flow area to increase, and thereby reducing the supply pressure that would be otherwise necessary to achieve a disc cavity flow adequate to maintain the temperatures within specifications.
Abstract:
A nuclear reactor plant has a nuclear reactor vessel in a containment vessel. Air ducts, sump discharge lines, service water lines and other non-process non-critical lines extending through the wall of the containment vessel can be isolated passively (i.e., without instrumentation and control systems or power) should a postulated event which raises the atmospheric temperature within the containment vessel occur. The passive containment isolation system includes an isolation valve disposed in the non-process line and an actuator responsive to the atmospheric temperature within the containment vessel. The actuator is operatively connected with the isolation valve for closing the non-process line in response to the atmospheric temperature. The actuator is preferably disposed in or adjacent a containment sump at the bottom of the reactor vessel or adjacent the reactor vessel cavity where the temperature of the local atmosphere will most rapidly rise.
Abstract:
A debris box is used in conjunction with a device for searching and retrieving a plurality of foreign objects (22, 24, 26) within a steam generator. The debris box (28) may include a container (56) for containing the objects. The container may include a drawer (60) having an opening (62) for inserting the objects therethrough, an enclosing mechanism for enclosing the objects within the container, and a motivating mechanism (76), such as a pneumatic cylinder, for opening and closing the container. The enclosing mechanism may be an elongated housing (70) which at least partially covers the drawer, substantially covers the opening (62) of the drawer (60) in the closed position, and at least partially uncovers the opening of the drawer in the open position. The container (56) may be a closable container which holds the objects and which has a closable opening for enclosing the objects within the closable container. The closable container may include a holder having an opening for inserting the objects therethrough and an elongated barrier which telescopes with the holder. The motivating mechaism telescopes the holder and the elongated barrier between the closed and open positions. The elongated barrier may substantially block the opening of the holder in the closed position and at least partially reveal this opening in the open position.
Abstract:
A method for removing scale, sludge, corrosion and other debris and deposits from the interior of a heat exchanger vessel such as a nuclear steam generator, includes generating pressure pulses in a non-corrosive, strongly basic, amine-containing chemical cleaning agent in aqueous solution after the agent has been introduced into the interior of the vessel. The chemical cleaning agent is an aqueous solution containing at least one of the group of lower alkyl amines and cyclic diimines or combinations thereof. The method further includes simultaneously recirculating the chemical cleaning agent through a filter assembly during the pressure pulsing operation in order to remove fluidized sludge and corrosion products dislodged by the pressure pulsing and chemical action. The method reduces the time required for a particular chemical cleaning agent to effectively clean the vessel and the number of times such chemicals need to be introduced into the vessel, which in turn results in the production of less radioactive liquid waste, and minimizes new corrosion through use of relatively non-corrosive cleaning agents.
Abstract:
A method and system for improved continuous ion exchange chromatographic elemental separations of zirconium and hafnium and also for isotopic separations thereof from crude zirconium minerals by using zirconium (also containing hafnium) sulfate feedstock solutions, sulfate eluant solutions, anionic exchange resins, and reduced ion exchange column operating temperatures. The method and system of the invention provides sulfate feedstock solutions by completely converting the carbochlorination products of zircon sand to sulfate solutions prior to feeding to the ion exchange chromatographic column. The method and system of the invention is performed in a continuously operating continuous annular chromatograph (CAC). Nuclear grade substantially purified zirconium and hafnium metals are produced.
Abstract:
An automated system for determining positions of a plurality of nuclear fuel assemblies organized in an array within a housing of a nuclear power plant includes a radiation hardened, underwater camera for inputting images of the nuclear fuel assemblies with respect to each other or with respect to a baffle wall of a nuclear reactor core, a digital signal processor for generating a second digitized image including a plurality of pixel elements of the nuclear fuel assemblies from the first image, and a workstation for determining the positions of the nuclear fuel assemblies with respect to the baffle wall from counts of the pixel elements.
Abstract:
An information system (2) manages functional units (12-20) having a function related to operation of an industrial process or electric energy enterprise (6), such as a nuclear utility. The functional units (12-20) maintain a knowledge set (26-34) representative of information pertaining to the function thereof. The information system (2) includes plural first databases (40-48) associated with the functional units (12-20) for storing the knowledge sets (26-34) maintained thereby; plural second databases (50-52) associated with entities (8-10); such as vendors (10) or other enterprises (8), external to the electric energy enterprise (6) for storing the knowledge sets (36-38) maintained by the entities (8-10); a remote communications network (4) for linking each of the first and second databases (40-52); a inquiry mechanism (66-76) for inputting an inquiry related to the first and second databases (40-52); and an artificial intelligence mechanism (78) for searching the first and second databases (40-52) in response to the inquiry in order to determine whether the knowledge sets (26-38) of the first and second databases (40-52) contain information pertinent to the inquiry, and to retrieve the information pertinent to the inquiry from the first and second databases (40-52).
Abstract:
A process for recovering iron from an iron oxide bearing mass. The process includes forming a bed (27) of lump coke (28) in a vertical shaft furnace (11), feeding the iron oxide bearing mass and scrap metal onto the bed (27) of lump coke (28) and combusting the coke (28) in the coke bed (27) while injecting a plasma gas having a temperature greater than about 5,000 DEG F into the coke bed to form a reaction zone (33) within the coke bed (27) having a temperature in excess of 4,000 DEG F. The iron oxide bearing mass and scrap metal fed onto the bed (27) of lump coke (28) is molten to form a molten phase containing molten iron oxide and molten scrap metal. The molten phase flows into the reaction zone and a film is formed on the lump coke within the reaction zone, the iron oxide in the film being reduced by carbon from the coke to form molten iron (22) in a solid/liquid reduction. The molten iron (22) is discharged from the furnace (11).
Abstract:
The system includes a distributed database (12) for maintaining the information over a lifetime of each of the nuclear power plant components, data entry terminals (14A, 14B, 14C) for entering the information in the distributed database, and data retrieval terminals (16A, 16B, 16C) for retrieving the information from the distributed database (12). The database (12) is distributed by a wide-area network (20) interconnecting the data entry and data retrieval terminals with distributed workstations (18A, 18B) which access the information.