Abstract: A cross point spacer is provided with subchannel vertical tubes at the subchannel volumes, these tubes being supplied with an inner flow free cylindrical volume and an peripheral steam separator in the form of a surface which imparts a spiral flow pattern to steam/water mixture flowing peripherally upwardly within the subchannel tube. According to a first and preferred embodiment, the subchannel tube of the cross point spacer is provided with rifling. According to a second embodiment, twisted vanes are installed and fastened to the interior of the subchannel tube and drilled away at the central portion of the twisted vanes to leave strips of metal defining rifling like paths on the subchannel tube interior. In either case, the main and central portion of the subchannel volume through the spacer is provided with an unobstructed central portion for upward steam flow.

Abstract: The present invention is directed to a modular steam separator with integrated dryer especially adapted for separating and drying steam exiting the core of a nuclear boiling water reactor. The instant modular separator with integrated dryer has a standpipe with a proximal end that is connectable to the upper plenum of the core of the nuclear reactor and a distal end that is connected to a proximal end of a steam separator. A distal end of the steam separator is connected to a steam distribution channel that extends in fluid communication to a steam dryer. The steam dryer has a steam vent for passage of dry steam to the steam dome of the reactor and a water drain connected to the reactor's downcomer region.

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: A method and an apparatus for locking the tie rods to block rotation relative to either the upper or lower tie plates utilizing the required fuel bundle channel. A conventional lock nut is provided for threading to the upper threaded end of the tie rods. This lock nut has attached extending wings, these wings when rotated interfering with a placed fuel bundle channel. In installation to the fuel bundle, and assuming that the tie rod has been fully threaded to the lower tie plate, the winged lock nut is rotated overlying the upper tie plate to cause full engagement of the upper tie plate to the tie rods. In such fastening, the winged lock nuts are rotated to an angle that provides no interference with the subsequently placed channel. Thereafter, and when the channel is placed, the channel interference with the rotational path of the wings of the lock nut and thus prevents relative rotation between the tie rod and winged lock nut.

Abstract: A phase-separator assembly for a boiling-water nuclear reactor includes a steam-separator and a dryer. The steam separator and dryer are mechanically coupled so that relative vertical movement is permitted therebetween. The mechanical coupling limits this relative vertical movement. When installed in a reactor, the steam separator and dryer are independently supported. The dryer is supported so as to define a gap between the dryer and steam separator that optimizes their collective performance. When in storage, the dryer is not independently supported. Instead, the dryer is dropped to a minimum height above the steam separator, providing for compact storage.

Abstract: An improved ferrule spacer for use with high density fuel rod arrays within boiling water reactor fuel bundles is disclosed. Ferrules are constructed in mating ferrule pairs. Each ferrule is divided into upper and lower ferrule halves. One ferrule half has sides thereof with the walls removed. The other ferrule half has its in place. The ferrule pairs are confronted with one ferrule inverted with respect to the other and with each complete ferrule wall of one ferrule half being juxtaposed to a ferrule half at a missing wall. Preferably, and at the point of tangency between the ferrule pairs, an aperture for receiving and confining an "H" type double loop spring is defined. The disclosure includes ferrules having a circular surround for the fuel rods and ferrules having an octagon sectioned surround for the fuel rods. Each member of the ferrule pair is symmetrical and completely interchangeable to provide for both convenient assembly and a small inventory of assembly parts.

Abstract: An automated monitoring system and method of operation is provided for a nuclear reactor having a pressure vessel containing a reactor core for boiling water to generate steam. A plurality of monitors provide signals for respective monitoring parameters for monitoring operation of the reactor, and a computer includes a database therein containing predetermined setpoints for the monitoring parameters. The computer identifies abnormal and normal behavior of the monitoring parameters based on the database, and determines cause of abnormal behavior of the monitoring parameters using artificial intelligence. A warning i also provided to identify the cause of the monitoring parameter abnormal behavior. And, automatic mitigation action may also be effected.

Abstract: A corium protection assembly includes a perforated base grid disposed below a pressure vessel containing a nuclear reactor core and spaced vertically above a containment vessel floor to define a sump therebetween. A plurality of layers of protective blocks are disposed on the grid for protecting the containment vessel floor from the corium.

Abstract: A method of manufacturing components made of zirconium-based alloy by combining heat treatment with thermal sizing. The heat treatment includes heating the component to a temperature which initiates the transformation from a hexagonal close-packed crystallographic phase of uniform texture to a body-centered cubic crystallographic phase and then quenching to a quench temperature at a rate which initiates transformation to a hexagonal close-packed crystallographic phase having a texture factor f.sub.L =0.28-0.38. The thermal sizing includes heating the component to a temperature less than the quench temperature, but sufficient to anneal the component, and then cooling. Preferably, the thermal sizing is performed twice: before and after the heat treatment.

Abstract: The remote inspection of seam welds in reactor vessels is improved through the utilization of a pulser network which is inductively isolated from the transducer circuit to which it applies an excitation signal. Through the utilization of a step-up transformer, the pulser network may perform in conjunction with linear d.c. power supplies of lower voltage rating. The inductive coupling between circuits also serves to provide for the positive communication off of switching devices such as SCRs employed for excitation signal triggering. To avoid ground path induced noise, a different ground path is employed for the pulser network as for the transducer circuit. The transducer circuit ground path is that associated with a manipulator and, for example, a reactor vessel itself. Thus, the transducers employed may come in contact with the surface of the vessel being inspected. In similar fashion, an inductive coupling is provided between the transducer circuit and a pre-amplfying receiver circuit.

Abstract: An improved internal standard for use in determining the concentration of decomposition products of tributyl phosphate in solvent used for solvent extraction. The improved internal standard includes deuterated variants of the decomposition products to be measured, e.g., deuterated dibutyl and monobutyl phosphoric acids. The use of deuterated dibutyl and monobutyl phosphoric acids eliminates the use of diazomethane, which is toxic and explosive, thereby providing a safer laboratory technique for routine analyses required to monitor production solvent extraction processes.

Abstract: A satellite heat removal means can be embodied as an original nuclear system feature but is especially adapted to be retrofitted to an existing nuclear reactor system to serve optionally to supplement heat removal from the system nuclear reactor containment upon happening of a LOCA, and to assume all system containment drywell venting in the event reactor core meltdown results in breach of the containment floor structure separating the containment drywell and wetwell space which breach would deprive the containment of a space to which a non-condensable fraction of LOCA generated heated fluid in the containment could be vented, cooled and stored. The satellite heat removal means includes a structural external of but preferably situated alongside the nuclear reactor containment. A heat exchanger surrounded by a pool of cooling water is located in an upper chamber of the structure while a pool of water is present in a lower chamber of the structure.

Abstract: A forced-circulation boiling-water reactor includes fluidic diodes in the coolant fluid return path between the pump deck and the core inlet plenum. The fluidic diodes permit a downstream flow to proceed relatively freely, but substantially resist upstream flow. When pumps are shut down, the fluidic diodes serve to augment natural circulation, thus enhancing core stability. When the pumps are operating, the fluidic diodes serve to resist backflow, minimizing any loss of pump efficiency. This direction-flow asymmetry imposed by the fluidic diodes is achieved without moving parts, so as to achieve a high level of reliability.

Abstract: A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber.

Abstract: A stator core for an electromagnetic pump includes a plurality of circumferentially adjoining groups of flat laminations disposed about a common centerline axis and collectively defining a central bore and a discontinuous outer perimeter, with adjacent groups diverging radially outwardly to form V-shaped gaps. An annular band surrounds the groups and is predeterminedly tensioned to clamp together the laminations, and has a predetermined flexibility in a radial direction to form substantially straight bridge sections between the adjacent groups.

Abstract: A multi-layer, rolled metal foil is laser tackwelded to form a tube which can be inserted in the intermediate space between the fuel body and cladding of a metal alloy fissionable fuel element. The rolled foil has at least three foil layers at the point of tack welding. The laser welding penetration is adjusted so that the foil weld is maintained at a thickness of at least two foil layers, but does not penetrate all of the layers. The weld is designed to fail in response to fuel or blanket alloy swelling during irradiation. After weld failure, the overlapping layers slip and the multi-layer foil unrolls as the fuel swells, providing a continuous, unbroken barrier between the fuel or blanket alloy and cladding which masks defects in the barrier due to weld failure.

Abstract: A pole storage caddy system includes a pole storage caddy for storing a set of service poles, a pole assembly work station, a motorized monorail pole hoist and a detachable auxiliary personnel work platform, all mounted on a rail truck-mounted rigid frame. The hoist is used to convey the pole sections between the storage caddy and work station during assembly and to support the weight of the pole assembly for in-vessel work. The pole assembly work station includes a two-position slotted keyway plate, the first position providing lateral restraint during torquing operations and the second position providing vertical support during pole assembly.

Abstract: A pressure suppression containment 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. The wetwell pool includes a plenum for receiving the non-condensable gas carried with steam from the drywell following a loss-of coolant-accident (LOCA). The wetwell plenum is vented to a plenum above the GDCS pool following the LOCA for suppressing pressure rise within the containment vessel. A method of operation includes channeling steam released into the drywell following the LOCA into the wetwell pool for cooling along with the non-condensable gas carried therewith. The GDCS pool is then drained by gravity, and the wetwell plenum is vented into the GDCS plenum for channeling the non-condensable gas thereto.

Abstract: A recirculation system for driving reactor coolant water in a downcomer within a reactor pressure vessel includes a jet pump disposed in the downcomer and having a suction inlet at the top thereof and an outlet at the bottom thereof. A reactor internal pump is joined directly to the pressure vessel at an access nozzle thereof and includes a housing sealingly joined to the access nozzle, and in serial flow communication an inlet channel, an impeller, an outlet channel, and an injector nozzle. The inlet channel carries coolant water from the pressure vessel to the impeller which pressurizes the coolant water and returns it through the outlet channel and the injector nozzle for injection into the jet pump inlet. The water injected from the internal pump into the jet pump drives the jet pump for effecting recirculation flow within the pressure vessel.

Abstract: A nuclear fuel bundle fuel transfer system includes a transfer pool containing water at a level above a reactor core. A fuel transfer machine therein includes a carriage disposed in the transfer pool and under the water for transporting fuel bundles. The carriage is selectively movable through the water in the transfer pool and individual fuel bundles are carried vertically in the carriage. In a preferred embodiment, a first movable bridge is disposed over an upper pool containing the reactor core, and a second movable bridge is disposed over a fuel storage pool, with the transfer pool being disposed therebetween. A fuel bundle may be moved by the first bridge from the reactor core and loaded into the carriage which transports the fuel bundle to the second bridge which picks up the fuel bundle and carries it to the fuel storage pool.