Westinghouse Electric Corporation

Westinghouse Electric Company LLC

James A Sparrow

Yuriy Aleshin

Robert K Gjertsen

Yu Chung Lee

Ronald P Knott

Frank J Baloh

Garry C Crabtree

Clarence D John, Jr

Peter H Beuchel

Robert J Fetterman

Keith J Drudy

Robert W Cantrell

Jeffrey T Alexander

Greg D Hill

Aleksey Slyeptsov

John J McEvoy

A VVER-1000 nuclear fuel assembly having a modified bottom nozzle with chamfers at the upper edge of the frustoconical transition from a hexagonal upper section of the nozzle to the lower circular end that mounts on a lower core support.

VVER-1000 fuel assembly bottom nozzle

The present invention provides a top nozzle for use with PWR nuclear reactors and power plants, and in particular, VVER nuclear reactors. The top nozzle includes a plate portion having a peripheral portion; a hub portion spaced from the plate portion; a plurality of support portions extending from the plate portion to the hub portion; and at least one deflector portion extending inwardly from the peripheral portion at an acute angle with respect to the plate portion.

Top nozzle and pressurized water nuclear reactor including same

The present invention provides novel fuel assemblies for use with PWR nuclear reactors and power plants, and in particular, VVER nuclear reactors. The fuel assemblies offer enhanced structural stability, skeletal rigidity, and distortion (bow and twist) resistance to support high burn-up fuel management. Each fuel assembly may include a plurality of fuel rods, a plurality of control rods and guide thimbles, at least one instrumentation tube, and a plurality of grids. At least one fuel rod is replaced with a structural support replacement rod made from zirconium (Zr) alloy, stainless steel, or any other suitable material. The structural support replacement rod may be hollow or solid. The structural support replacement rods are preferably disposed at or about the periphery, and in some cases, the corners of the geometric array, which is preferably a hexagon or square.

Nuclear fuel assemblies with structural support replacement rods

An integral multilevel debris-catching system for a nuclear reactor fuel assembly having a lower protective grid incorporating laterally offset debris-catching arches at several elevations, extended solid fuel rod bottom end plugs and a bottom debris-filtering nozzle. Dimples and opposing opposite springs and the debris-trapping arches, which are spaced from the end plugs, are all located at elevations below the fuel cladding.

Nuclear fuel assembly protective grid

A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its upper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.

Tube-in-tube threaded dashpot end plug

A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its tipper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.

An advanced gray rod control assembly (GRCA) is for a nuclear reactor. The reactor has a plurality of fuel assemblies each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug, a substantially pure silver neutron-absorber disposed within the tubular member, and a support tube surrounding the neutron-absorber within the tubular member to resist silver-swelling. Delta-power of the reactor is improved by minimizing the exposed surface area of the absorber and distributing it among all of the rods of the GRCA.

Advanced gray rod control assembly

A high energy absorption top nozzle for a nuclear fuel assembly that employs an elongated upper tubular housing and an elongated lower tubular housing slidable within the upper tubular housing. The upper and lower housings are biased away from each other by a plurality of longitudinally extending springs that are restrained by a longitudinally moveable piston whose upward travel is limited within the upper housing. The energy imparted to the nozzle by a control rod scram is mostly absorbed by the springs and the hydraulic affect of the piston within the nozzle.

High energy absorption top nozzle for a nuclear fuel assembly

Disclosed is a grid structure for supporting fuel rods in a nuclear reactor. The grid structure is formed of a plurality of interconnected thin metal grid straps that are welded or brazed together to provide a structural network of interconnected open grid cells, similar to an 'egg crate divider'. The grid straps are provided at regular intervals, corresponding to the width of a grid cell, with pairs of spaced, substantially horizontal, slotted spring-like projections and a substantially X-shaped spring-like projection vertically intermediate the horizontal projections. The spring-like projections are designed to support and hold the fuel rods within the grid cells under both balanced and unbalanced forces acting on the fuel rod assembly while it is in service, surrounded by coolant in the nuclear reactor.

Grid structure for supporting fuel rods in a nuclear reactor

A double enclosure top nozzle subassembly for a nuclear fuel assembly includes an upper structure having a top plate and an outer depending peripheral sidewall enclosure, a lower structure having a lower adapter plate and an inner upstanding peripheral sidewall enclosure disposed below the top plate and within the outer sidewall enclosure. The outer and inner sidewall enclosures are slidably movable relative to one another as the top plate moves toward and away from adapter plate. A plurality of resiliently-yieldable biasing devices, such as leaf springs extend between and engage the top plate and lower adapter plate. Interengagable structure on the lower and upper edges of the respective outer and inner sidewall enclosures limit movement of the top plate and lower adapter plate away from one another so as to retain the outer and inner sidewall enclosures in sliding contacting relationship together. The leaf springs are movable between compressed and expanded states in response respectively to application and removal of a hold-down force on the upper structure in the direction of the lower structure for permitting and causing movement of the top plate toward and away from the adapter plate and thereby the top nozzle subassembly between compressed and expanded conditions.

Nuclear fuel assembly having double enclosure top nozzle subassembly

A reconstitutable control assembly has a spider structure which supports control rods by detachable attachment joints. Each attachment joint includes a hollow connecting finger on the spider structure and an elongated detachable split upper end plug on each control rod. The split upper end plug includes a pair of separate upper and lower plug portions. The upper plug portion has upper, middle and lower sections, whereas the lower plug portion has upper, middle and lower segments. The upper section of the upper plug portion is rigidly attached to the connecting finger on the spider structure, whereas the lower segment of the lower plug portion is rigidly connected to the control rod. Also, the lower section of the upper plug portion and the middle segment of the lower plug portion have complementary threads defined thereon for rigidly threadably attaching the upper and lower plug portions to one another. Two embodiments of locking features can be used in conjunction with the upper and lower plug portions for locking them together so as to resist their unthreading from one another.

Reconstitutable control assembly having removable control rods with

A method of removing bow in a nuclear fuel assembly is disclosed. The fuel assembly has top and bottom ends fittings and a plurality of longitudinally extending thimble tube members interconnecting top and bottom end fittings. At least two transverse fuel rod support grids are axially spaced along the thimble tube members. A plurality of fuel rods are transversely spaced and supported by the fuel rod support grids. In one embodiment, a weight of known magnitude is secured on the bottom end fitting and the fuel assembly is raised with the weight secured thereon so that the weight exerts a downward force on the fuel assembly for straightening the fuel assembly and eliminating compressive stresses within the fuel assembly. In another embodiment, the bottom end fitting is secured onto the upender used for transporting fuel assemblies into and out of the containment building and the fuel assembly is pulled for straightening the fuel assembly and eliminating compressive stresses within the fuel assembly.

Method of straightening a bowed nuclear fuel assembly

A dashpot in a control rod guide thimble for a nuclear fuel assembly includes a lower tubular portion of an elongated main tube of the guide thimble, an auxiliary hollow tube inserted in the lower portion of the main tube, and an end plug attached to a lower end portion of the auxiliary tube. The auxiliary tube has an outside diameter slightly less than an inside diameter of the main tube to permit a close fitting relationship between an exterior surface of the auxiliary tube and an interior surface of the main tube lower portion. The auxiliary tube also has an upper end portion with an inside surface portion in axial cross-section flaring upwardly and outwardly to provide a tapered transition extending between and connecting an interior surface of the auxiliary tube with the exterior surface thereof.

Dashpot construction for a nuclear reactor rod guide thimble

An expandable top nozzle subassembly for a nuclear fuel assembly includes an upper structure having a top plate and a depending peripheral sidewall enclosure, a lower adapter plate disposed below the top plate and within the enclosure with the adapter plate and sidewall enclosure being slidably movable relative to one another so as to move the top plate toward and away from adapter plate, and a plurality of resiliently-yieldable biasing devices extending between and engaging the top plate and lower adapter plate. Interengagable structure on a lower edge of the enclosure and on a peripheral edge of the adapter plate capture and retain the adapter plate within the enclosure upon movement of the enclosure relative to the adapter plate which moves the top plate away from the adapter plate. The biasing devices in the form of coil springs are movable between compressed and expanded states in response respectively to application and removal of a hold-down force on the upper structure in the direction of the adapter plate for permitting and causing movement of the enclosure relative to the adapter plate so as to move the top plate toward and away from the adapter plate and thereby the top nozzle subassembly between compressed and expanded conditions.

Growing community of inventors

Columbia, SC, United States of America

James A Sparrow