Abstract: In an embodiment of the present invention, the core of a nuclear reactor includes a plurality of fuel cells and a plurality of large control rods. Each large control rod is about two times the width of a conventional control rod and includes four control rod blades extending radially from a central portion and arranged at right angles to each other. The blades define four fuel bundle receiving channels. The core is configured so that the control rods are-arranged in a plurality of staggered rows with four fuel bundles in each receiving channel.

Abstract: The present invention, in one form, is a natural circulation reactor having, in one embodiment, a layer of high aluminate cement concrete disposed between an uninsulated steel liner and a prestressed concrete reactor vessel. The prestressed concrete reactor vessel includes a concrete shell having a cavity therein. The steel liner is positioned in the cavity and spaced from the concrete shell so that an insulating chamber is formed between the steel liner and the concrete shell. The insulating chamber is filled with high aluminate cement concrete which is configured to substantially insulate the concrete shell from the steel liner and to transfer loads such as pressure from the liner to the concrete shell.

Abstract: Fuel bundle and control rod assemblies for a nuclear reactor are described. In one embodiment of the apparatus, the nuclear reactor includes several conventional size fuel bundles and at least one large control rod. The large control rod includes four fuel bundle receiving channels, and each such channel is sized to receive four conventional size fuel bundles.

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: A boiling water reactor includes a pressure vessel containing a reactor core, chimney, steam separator assembly, and steam dryer assembly therein, with the vessel being filled with reactor water to a normal water level through the steam separator assembly. A plurality of control rod drives extend downwardly from the bottom of the pressure vessel and are operatively joined to control rods extending downwardly into the reactor core. The chimney includes a plurality of channels disposed above the core and laterally spaced apart to define guide slots for receiving the control rods as they are selectively translated upwardly out of the core by the control rod drives. The chimney has a vertical height for increasing the normal water level above the reactor core and for providing a space for the control rods withdrawn from the reactor core by the bottom-mounted control rod drives.

Abstract: A reactor core with each fuel rod surrounded by an individual cylindrical channel is disclosed. This individual channel on each fuel rod provides thermal hydraulic and heat transfer advantages to enable all fuel rods within the fuel bundle to uniformly approach their own thermal limits. The preferred fuel rod pitch is a triangular pitch between the individual fuel rods as they are discretely surrounded by their own channel. The new triangular geometry provides for more uniform (flat) power distributions within all fuel rods--and hence all groups of fuel rods. Bypass flow is introduced uniformly between the fuel rod channels, rather than heterogeneously in the channel gap and water rods as in present BWR fuel designs. Individual fuel rod channels can be orificed differently, as required, to match inlet flow to fuel rod power output to maintain uniformity between all fuel rods as they approach their respective thermal limits.

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 reactor building assembly includes a pressure vessel within a containment vessel surrounded in turn by first and second enclosures defining respective first and second chambers. A method of operation includes channeling fresh air downwardly by gravity through the second chamber and then channeling the fresh air laterally through the first enclosure adjacent to the bottom thereof and into the first chamber. The air is then channeled upwardly by natural buoyancy through the first chamber for cooling the first chamber and mixing with stale air therein. The stale air is then discharged from the first chamber upwardly through the top of the first enclosure to the environs.

Abstract: An expanded reactor core capacity is achieved within the constraints imposed by the diametric extent of the current advanced boiling reactor (ABWR). This enhanced core capacity is achieved through the utilization of a scalloped shroud structure in conjunction with modified control rod designs. The core diameter is expanded toward the reactor vessel interior wall to establish a minimum distance therebetween representing a minimum value thereof avoiding neutron fluence induced vessel embrittlement. The control rods servicing peripheral fuel assemblies are configured having either a T-shaped blade configuration or an L-shaped blade configuration depending upon the parallel orientations of the peripheral fuel assemblies.

Abstract: Fuel management in a boiling-water nuclear reactor involves arranging fuel bundles in upper and lower matrices of the reactor core. During a refueling operation, some bundles in the upper matrix are removed and retired, while fresh bundles are inserted in the lower matrix and some bundles originally in the lower matrix are transferred to the upper matrix. In the transfer, fuel bundles are inverted so that included fuel rods in the lower matrix have their plenums oriented downward, while fuel rods in the upper matrix have their plenums oriented upward. This method provides greater flexibility in repositioning fuel bundles for longer burnups and lower high-level waste. In particular, problems with axial spectral variations in neutron flux can be compensated for using the disclosed refueling procedure.

Abstract: A nuclear reactor with a recirculating heat transfer fluid has a bi-level core which provides enhanced flexibility in fuel arrangement. The bi-level core includes a first core, a plurality of steam separators disposed above the first core, and a second core disposed above the steam separators all inside a single pressure vessel. The steam separators receive a steam and water mixture from the first core and separate the water from the steam. The separated steam is channeled to the second core which cools the second core resulting in the generation of superheated steam. Preferably, fuel bundles of the second core are arranged in vertical alignment with fuel bundles of the first core. This permits a fuel bundle of the first core to be accessed by removing only the adjacent fuel bundle of the second core. During refueling operations, fuel bundles can be shifted from one core to the other, providing additional flexibility in arranging units at various states of burnup.

Abstract: A method for affecting neutron spectral shift in a reactor core includes providing a liquid poison in a hollow control blade extending into the core, displacing the liquid poison with a first fluid for obtaining a hard neutron spectra during a beginning interval of the core fuel cycle for converting fuel, and then increasing moderating ratio for obtaining a soft neutron spectra during an end interval of the cycle for burning the converted fuel. An exemplary apparatus for practicing the method displaces the liquid poison in the control blade with the first fluid for obtaining the hard neutron spectra. The first fluid may be either replaced, displaced, or added to by a second fluid having a second moderating ratio for obtaining the soft neutron spectra.

Abstract: A fuel bundle of square cross section and standard vertical dimension is disclosed. The fuel bundle includes a matrix of upstanding vertical rods, a lower tie plate for supporting the matrix of vertical rods and permitting the inflow of liquid moderator coolant (preferably light water), and upper tie plate for holding the matrix of vertical fuel rods upright and permitting the outflow of liquid and vapor moderator coolant (water and steam), and a preferably square sectioned channel extending between the tie plate for confining the flow path between the tie plate around the fuel bundle. The novel characteristics of the invention is the introduction of a corresponding matrix of water rods (cylindrical rods with liquid phase water flow) positioned between the fuel rods, as opposed to the current practice of using or displacing a subset of fuel rods with large central water rod(s) for this purpose.

Abstract: In accordance with the present invention, a nuclear reactor with a recirculating heat transfer fluid has a bi-level core which provides enhanced flexibility in fuel arrangement. The bi-level core includes two sets of fuel units, one set arranged on a first level, the other set arranged on a second level. Preferably, fuel units of the second level are arranged in vertical alignment with fuel units of the first level. This permits a fuel unit of the first level to be accessed by removing only the adjacent fuel unit of the second level. During refueling operations, fuel units can be shifted from one level to the other, providing additional flexibility in arranging units at various stages of burnup. Preferably, fuel units of the first level are inverted relative to the fuel units of the second level.

Abstract: A BWR coolant recirculation system includes a pump deck disposed in a downcomer and fixedly joined to a reactor pressure vessel and reactor core shroud. A plurality of circumferentially spaced reactor internal pumps (RIPs) are joined to the deck and operable in a pumping mode for pumping downwardly a reactor coolant from the downcomer and into a core inlet. In a pump inoperable mode, a portion of the coolant bypasses the RIPs for allowing increased natural recirculation of the coolant from the downcomer and into the core inlet.

Abstract: A reactor core includes upper and lower matrices of fuel bundles. Fuel rods in the upper matrix have their plenums oriented upward, while fuel rods in the lower matrix have their plenums oriented downward. Refueling involves removal of a first bundle in the upper matrix, removal and retirement of the bundle in the lower matrix directly below the original position of the first bundle, inversion and installation of the first bundle in the lower matrix, and installlation of a new bundle in the upper matrix. The new bundle is installed plenum-side up. The bi-level core provides greater flexibility in repositioning fuel bundles for longer burnups and lower high-level waste. In particular, problems with axial spectral variations in neutron flux can be compensated using the disclosed core arrangement and refueling procedure.

Abstract: A steam separator for a boiling water reactor includes a pressure vessel and a chimney spaced radiallly inwardly therefrom to define a downcomer therebetween for recirculating water, the chimney being disposed above a reactor core for channeling upwardly therefrom steam voids and water flow. An annular partition wall is spaced radially between the vessel and he chimney to define an annular collection chamber having an inlet for receiving a portion of the steam voids and water flow from the chimney, a steam outlet for discharging the steam voids from the chamber, and a flow outlet for discharging the water flow from the chamber into the downcomer.

Abstract: A recirculation system for a boiling water reactor includes a plurality of circumferentially spaced impeller-driven reactor internal pumps disposed in a downcomer for pumping a first portion of reactor coolant, and a plurality of circumferentially spaced fluid-driven jet pumps disposed in the downcomer for pumping a remaining portion of the coolant in the downcomer. In an exemplary embodiment, the jet pumps are driven by a portion of feedwater provided to the reactor.

Abstract: A safety qualified interface device is interposed between an operator manned control position having an operator interface and qualified safety system logic monitoring and control devices. This microprocessor driven interface incorporates a memory carrying a library collection of valid safety directives as well as valid parameter inputs and permissible parameter deviation ranges. Control or parameter requests are asserted by the operator from non-safety related but conveniently positioned interface devices at the control position which are treated as trial inputs which are matched at the interface with memory retained valid directives and parameters. Where a match between memory retained data and the trial input signals occurs, then the operator is apprised through a qualified safety related display and a corresponding acknowledgement is made to the interface.

Abstract: A method and arrangement for operating a boiling water nuclear reactor and fuel assembly designs for such reactor wherein the reactor is operated with uniquely located control rods that serve the primary functions of power shaping and reactivity control. A second and separate distinct group of control rods is withdrawn when the reactor is at power and the control rods of this group serve the primary function of reactor shutdown. The design of the fuel assemblies and the selected patterns of fuel assemblies and control rods make the separation of control functions feasible. The power shaping and reactivity control control rods are located in low power regions of the core designated control cells. The design of the fuel is such that the control rods of the control cells may remain in fixed positions in these cells during the operating cycle until withdrawal for burnup reactivity compensation.