Abstract: A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

Abstract: A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.

Abstract: A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.

Abstract: A direct vessel injection (DVI) nozzle for minimum emergency core coolant (ECC) bypass is disclosed. The DVI nozzle is used in a pressurized light water reactor (PLWR) having a reactor vessel with a reactor coolant system in which a coolant flows into the reactor vessel through a cold leg and passes through a reactor core prior to being discharged to the outside of the reactor vessel through a hot leg. The DVI nozzle, provided to directly inject ECC into the reactor vessel to cool the reactor core during a break in the reactor coolant system, such as a cold leg break (CLB) that may occur in the PLWR, is placed on the reactor vessel at a position horizontally offset from the central axis of the hot leg at an angle of 10° to 30° and is involved within a region defined above the central axis of the hot leg by a distance of 1.5 times the sum of diameters of the hot leg and the DVI nozzle.

Abstract: The present invention relates to a fuel assembly for a light-water reactor with a substantially square cross section wherein the fuel assembly comprises a plurality of fuel rods (4). The fuel rods (4) extend between a bottom tie plate (5) and a top tie plate (6) and a coolant is adapted to flow upwards through the fuel assembly. At least one of the top tie plates (6) or the bottom tie plates (5) comprises flow openings (22, 22a, 22b) for the passage of the coolant and side supports (17) for supporting the fuel rods (4) in the lateral direction. The side supports (17) are designed in one and the same sheet-metal piece as the flow openings (22, 22a, 22b) and the side supports (17) are folded substantially 90° in relation to the other structure of the top tie plate (6) or the bottom tie plate (5).

Abstract: In order to support a shroud against bending, shear, stress and torsion, straps which are preferably formed of the same material as the shroud, are placed in strategic positions with respect to cracks or the like type of weaknesses which have been detected, and fastened in place using a suitable fastening technique. In the preferred embodiments of the invention holes a formed using an EDM technique and bolt units which have an expanding portion are inserted into the holes, torqued and expanded in a manner which fastens the strap to the shroud. Welding and the like type of fastening techniques are not excluded and may used alternatively or in combination with the bolting technique as required.

Abstract: In order to eliminate the need to weld, drill or otherwise machine a shroud structure which is used to surround a plurality of fuel assemblies in a nuclear reactor, a plurality of upper hanger rods interconnect a structure above the shroud to a support ring which is clamped about the upper periphery of the shroud. Lower hanger rods interconnect a lower edge or shoulder portion of the shroud with the support ring. Thus, through the upper and lower hanger rods and the support ring, the shroud can be supported within the RPV. The upper support ring is arranged to clamp the lower ends of the upper hanger rods against the upper outer peripheral portion of the shroud while the lower ends of the lower hanger rods are clamped against the lower peripheral wall portion of the shroud by a lower support ring.

Abstract: A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

Abstract: A pressurized water reactor has a solid reflector formed of a stack of rings each completely surrounding the reactor core, whose internal periphery matches the external contour of the core. Keys fixed to the casing project into vertical grooves formed in the rings for centering them with respect to the core casing. The stack is formed with a plurality of vertical channels each consisting of a plurality of vertical mutually aligned passages each formed in a respective one of said rings, each channel containing a plurality of vertically aligned plugs.The vertical passages are formed in radially thicker parts only of the rings. Each plug cooperates with the respective ring to define an annular water flow channel. Some at least of the plugs comprise an upper flange bearing on a shoulder of a corresponding ring, machined for defining channels slanted with respect to the vertical so as to give a circumferential speed component to the water flowing along the annular passages about the plugs.

Abstract: A partitioning device is provided which can be used in a pressurized water nuclear reactor. It occupies the space between the prismatic shaped core of the reactor, and a cylindrical casing and comprises vertical partitioning plates surrounding the core and reinforcement elements placed between the partitioning plates and the casing. It comprises panels distributed into horizontal rows in vertical columns, all the panels of the same row being identical and having vertical partitioning plates welded together and fast with criss-crossed horizontal and vertical reinforcements bearing on the casing and with vertical tubes. The stacked tubes of a same column form a post resting on a core support plate. Solid vertical keys connect the panels in the different columns together and to the casing.

Abstract: Upper internals for a pressurized nuclear reactor include an assembly for collecting the coolant leaving the core and a separating device. The device has guides for the control clusters and their drive shafts, a lower plate formed with passages for the coolant leaving the core and an upper plate formed with holes for passage of the same coolant into the collection assembly or plenum. A peripheral shroud may connect the plates together. Each cluster guide of the flow separation device has an internal casing devoid of openings, having a practically coolant-tight connection with the plates, whereby the control clusters and their drive shafts are protected against the high speed coolant flow from the core to the outlet nozzle.

Abstract: High temperature reactor with residual-heat transfer system comprises a cooling gas intake at the bottom and cooling gas outlet at the top so that a cooling gas can flow from the bottom to the top through the reactor core. In order to assure reliable heat transfer a bypass duct is provided with a lower end communicating with the cooling gas intake and the upper end communicating with the cooling gas outlet. The bypass duct is arranged parallel to the reactor core and passing a partial flow of cooling gas from the bottom to the top. This partial flow of cooling gas heats up only trivially. This partial flow of cooling gas is further cooled by the cooler. The upward flow of the comparatively cold cooling gas in the bypass duct stops and by itself reverses because the cooling gas in the bypass duct is drawn toward the reactor core on account of the natural convection.

Abstract: During a shutdown of the reactor, a device for partially closing off (27) the openings (26) of the reinforcements (6) located below the upper reinforcement (6a) is introduced through the opening (25) of the upper reinforcement (6a) of the partitioning of the core of the reactor. The closing off devices (27) remaining in position in the partitioning of the reactor after restarting thereof permit the increase and regulation of the head loss of the cooling water circulating in the annular space (7) around the partitioning (5) of the core. The closing-off device may consist of a rod (27) engaged in a set of openings (26) of the reinforcements (6) aligned along a vertical direction.

Abstract: A new design for nuclear reactor internals resulting in reduced fast neutron leakage to the reactor vessel. The first step of the two-stage process reflects high energy or fast neutrons back into the core, by placement of a reflector made of tungsten, stainless steel, or zirconium oxide in the baffle barrel region. The second stage involves reducing the energy of any fast neutrons that may pass through the reflector by the use of a neutron energy reducer, composed of an hydrogenous material such as titanium hydride, surrounding the core barrel in the areas of high neutron flux. In addition to protecting the reactor vessel wall and increasing the operating life of a nuclear reactor, the neutron economy in the core, and hence the operating efficiency of a nuclear power plant, are significantly increased.

Abstract: A pressurized water nuclear reactor with solid partitioning comprises a core formed by assemblies of prismatic shape disposed side by side inside a vertical cylindrical casing. A space between the core and the casing receives a solid partitioning structure. The partitioning is formed as a vertical stack of rings each completely surrounding the core, whose external periphery is engaged with a clearance in the casing and whose internal periphery matches the external contour of the core. The rings are centered and indexed with respect to the core casing by keys fixed to the casing and projecting into vertical grooves formed in the rings and they are formed with vertical mutually aligned holes defining cooling channels. Plugs in the channels define restricted water flow passages.

Abstract: Modular neutron reflector assemblies removably insertable into the irregular space in a nuclear reactor between a generally cylindrical array of square fuel assemblies comprising the core and the cylindrical core barrel surrounding the core, include an elongated enclosure having a strongback adjacent the core barrel and flat plates adjacent the fuel assemblies. The strongback is thicker than the steel plates by an amount which results in the strongback and plates reaching approximately the same temperature to minimize thermal stresses despite the 8 to 20 times greater nuclear heating at the core side of the enclosure as opposed to that at the core barrel side. The enclosure is suspended by a single point mounting on the core barrel which permits vertical, radial, and circumferential expansion but a pin depending from the lower end of the enclosure slides in a vertical bore in the reactor lower core support plate to limit lateral movement while allowing unrestrained vertical expansion and contraction.

Abstract: Nuclear reactor having upper internal equipments and lower internal equipments with probe guiding means including probe guide ducts for slidably guiding flexible elongated probes into the core. The upper internal equipments include a plenum chamber for collecting the coolant coming out of the core and separating means disposed between the core and the plenum chamber, said separating means including two plates, one upper and one lower, connected at their periphery by an envelope and comprising spacer tubes through which pass the coolant so as to avoid passing through cluster guides for guiding the clusters of control elements into and out of the core. Lower internal equipments placed between the core and the bottom of the vessel include an enclosure and ducts for the passage of the coolant entering the core, said enclosure thus defining a tranquilized volume in which the probe guide ducts are distributed.

Abstract: An improved plugging system for plugging chamfered flow ports of small diameters in the core barrel of a pressurized water nuclear reactor is disclosed herein. The system is comprised of improved core barrel plugs that are telescopically contractible to facilitate installation, as well as a handling tool having a compact hydraulic ram and plug-holding cradle that is easily manipulable in the limited access space between the core barrel and thermal shield of the reactor for inserting and expanding the plugs into sealing engagement with the core barrel flow ports. The plugs of the system are formed from a generally cylindrical plug body that is radially expandible, and a retaining ring that is telescopically engaged around the plug body which allows it to be slid toward the middle of the plug prior to installation in order to minimize the overall length of the plug prior to the insertion operation.

Abstract: A method for converting a vertically downward flow of bypass coolant through coolant flow holes in a core barrel and former plates in a nuclear reactor to a vertically upward flow. Coolant flow holes are provided in the normally solid top former plate by suitable means such as drilling. These new coolant flow holes are located so as to be substantially in coaxial alignment with the existing coolant flow holes in the intermediate and lower former plates. Existing coolant flow holes in the core barrel adajcent the top former plate are plugged. Existing coolant flow holes in the lower former plate are plugged in an alternating pattern with each fifth hole being plugged having only forty-four percent of its flow area plugged.

Abstract: A high flux reactor is comprised of a core which is divided into two symetric segments housed in a pressure vessel. The core segments include at least one radial fuel plate. The spacing between the plates functions as a coolant flow channel. The core segments are spaced axially apart such that a coolant mixing plenum is formed between them. A channel is provided such that a portion of the coolant bypasses the first core section and goes directly into the mixing plenum. The outlet coolant from the first core segment is mixed with the bypass coolant resulting in a lower inlet temperature to the lower core segment.

Abstract: A radial neutron reflector is disclosed for a light water nuclear reactor. The irregular space between the core periphery and the core barrel surrounding the core is filled with a structure comprising material other than hydrogen such as zirconia or stainless steel so as to displace the reactor water coolant in this region. The structure is provided with appropriately sized flow holes to pass reactor coolant therethrough and to balance the pressure within the structure to substantially coincide with the axial pressure profile at the core periphery.

Abstract: A nuclear reactor with juxtaposed prismatic fuel assemblies cooled by the flow of a liquid in a cylindrical jacket. A partitioning of the core between the peripheral assemblies and the jacket is constituted by rods parallel to the assemblies, guided laterally by bracing plates fast to the jacket in which the rods are free to slide longitudinally.

Abstract: Both an apparatus and process for providing a coolant flow path in the top former plate of the core of a nuclear reactor are disclosed. The apparatus of the invention generally comprises an elongated tool support member having a tool mounting means for detachably mounting various tools in the vicinity of the top former plate, and a clamp assembly for securing and positioning the tool mounting means over the plate. The apparatus also includes an ultrasonic transducer (or probe) for measuring the thickness of the plate, a rotabroach device having a feed and drive assembly for driving a pilot drill bit and a rotabroach bit toward the top former plate, and a piercing tool for removing the slug formed by the rotabroach bit. In the process of the invention, an alternate coolant flow path is provided in the top former plate by boring a plurality of holes therethrough.

Abstract: The invention comprises a core barrel plug capable of being remotely installed in a port of a core barrel of a pressurized water nuclear reactor for converting the reactor from a by-pass downflow configuration to a by-pass upflow configuration. The plug comprises a body having an expandable cylindrical portion with a movable mandrel disposed in the body. Remote fluid pressurization causes the mandrel to be advanced thus expanding the body into contact with the port. The plug also comprises a locking mechanism to prevent inadvertent release of the plug and a venting mechanism to prevent inadvertent overpressurization of the plug.

Abstract: A device for partitioning off the core of a nuclear reactor, including transverse plates (17) attached to the envelope (8) of the core and arranged transversely with respect to the fuel assemblies (5), and second plates (19) extending in the longitudinal direction with respect to the fuel assemblies. The second plates (19) are arranged in gaps between the transverse plates (17) and slightly stepped back with respect to the assemblies (5). The transverse plates (17) are connected to the longitudinally extending plates (19) with a certain clearance in the longitudinal direction. The transverse plates (17) are in contact with the assemblies (5) arranged at the periphery of the core by way of a portion of their peripheral surfaces.

Abstract: Apparatus for partitioning off the core of a nuclear reactor constituted by a set of boxes (8, 9, 10, 11) each comprising at least two plates (12-13, 14-15, 27-29, 28-30) rigidly assembled at right angles and disposed in the longitudinal direction of the assemblies, and a plurality of transverse plates (32) perpendicular to the longitudinal plates. The boxes are removably disposed side by side inside the core casing (1), and bearing thereon. The faces of the longitudinal plates directed towards the reactor core serve as bearing faces for the assemblies. Each of the boxes is fixed to at least one of the upper or lower plates of the core by a flexible coupling allowing longitudinal displacement.