General Electric Company

Michael V Curulla

Eric B Johansson

Bruce Matzner

John F Price

Robert B Elkins

Victor M Horn

Gerald M Latter

Jaime A Zuloaga, Jr

Frank D Qurnell

Kenneth Wood Brayman

David W Danielson

Carl R Mefford

Jerry T Spell

Leaf-type springs are inserted into slots in an upper tie plate of a nuclear fuel assembly and bear against interior surfaces of the fuel channel to center the upper tie plate within the fuel channel. More robust similarly configured leaf springs are secured in slots in the upper tie plate and are cantilevered for bearing engagement through slots in the fuel assembly channel against the reactor top guide to bias the fuel assemblies toward the control rod. To mount each spring to the upper tie plate, the base of each leaf spring includes a central beam and a pair of outermost beams spaced from the central beam, all beams lying in a common plane. Laterally outwardly directed tabs are provided on the lower ends of the outer beams. Stops are provided intermediate the ends of the outer beams. By inserting the unstressed, unloaded base of the springs into the slots, the outer beams are displaced inwardly into a stressed condition. Once the tabs extend past the lower surface of the tie plate, the beams return to an unloaded, unstressed condition with the tabs and stops locking the springs to the tie plate. The distal ends of the springs bear against the channel or top guide, as applicable, to locate the upper tie plate within the channel and bias the fuel assembly and channel toward the control rod, respectively.

Spring retention of upper tie plate and fuel bundle channel in a nuclear

A spring-and-spacer assembly for maintaining fuel rods upright in a fuel assembly of a nuclear reactor core is provided. The spring is in the form of a continuous loop with first and second legs having mid-leg rod-contact regions. Bend regions are positioned on each side of each contact region extending toward the interior of the loop spring. In most positions, the spring is used to load two adjacent fuel rods. In configurations in which there is an unpaired fuel rod, a plate having a tab for contacting the spring is provided. The spring provides the desired force, such as about 2.5 pounds per fuel rod, in a small rod-to-rod spacing of less than about 0.14 inches.

Nuclear fuel assembly spacer and loop spring with enhanced flexibility

An improved upper tie plate is disclosed in a fuel bundle for a boiling water nuclear reactor. The tie plate resides in a fuel bundle including an upper tie plate, a lower tie plate, a matrix of sealed fuel rods supported therebetween, and a surrounding channel. Both the lower tie plate and the improved upper tie plate have two functions; they support the fuel rods in vertical upstanding relation between the tie plates and interior of the channel and permit the passage of moderating coolant through the channel from the bottom of the channel to the top of the channel. This moderating coolant enters through the lower tie plate in the liquid form, passes into the matrix of upstanding fuel rods where steam is generated and exits outwardly through the improved upper tie plate as a water steam mixture at the top of the fuel bundle. The improvement includes the support of the channel directly from the fuel bundle lifting bail for transmission of load directly to the bail instead of a cantilevered support through the tie plate. This direct support enables cutting away a portion of the matrix overlying the fuel rods for reduction of pressure drop in the escaping steam/water phase from the fuel bundle. Additionally, this alignment enables raising of the points of tie plate support for longer fuel rod length. Improved fuel bundle performance results.

Upper tie plate for boiling water nuclear reactor

An improved lower tie plate having increased fluid flow resistance is disclosed for use in a boiling water nuclear reactor. The fuel bundle includes the lower tie plate, an upper tie plate, and a plurality of fuel rods supported therebetween in vertical upstanding relation, with the fuel rods surrounded by a square sectioned channel. In the preferred embodiment, some of the upper fuel rods are of partial length. The surrounding channel confines the fluid flow through the fuel bundles between the tie plates for the extraction of heat from the fuel rods undergoing a fission reaction. The lower tie plate includes a first group of apertures for the support of the fuel rods to selected positions in the 9x9 matrix; appropriate numbers of these apertures are threaded for tying the upper and lower tie plates together with tie rods. The matrix is interrupted at larger apertures for the support of moderator containing water rods. The tie plate also includes a second matrix of through holes acting as fluid energy dissipation orifices. These fluid energy dissipation orifices include a first small downwardly exposed fluid receiving aperture which discharges to a second and larger upwardly exposed flow area preferably formed in the shape of a concentric aperture. In the preferred embodiment the inlet to the first concentric and small downwardly exposed fluid receiving aperture is rounded for the intake of fluid with maximum flow predictability. The outlet from the first concentric and small downwardly exposed fluid receiving aperture is abrupt to produce maximum predictable energy dissipating turbulence in the upwardly exposed fluid discharge area. Passage of fluid through the energy dissipation apertures causes an increased pressure drop at the lower tie plate, for the suppression of thermal-hydraulic flow instabilities, and coupled thermal-hydraulic nuclear instabilities. A serendipitous effect is present in that the increased pressure drop causes uniform fluid flow in the interior of the fuel bundle immediate the lower tie plate.

Lower tie plate with stepped holes to control pressure drop and flow

In a nuclear fuel bundle, an improved lock washer is disclosed for permitting ease of remote removal of hex nuts on tie rods for the remote submerged disassembly of fuel bundles after use in a reactor. The improved lock washer includes two spaced apart and interconnected tie rods surrounding washer members, each of these tie rod washer members having radially inwardly extending keys. These keys register to corresponding keyways in the threaded ends of the tie rods to prevent tie rod rotation and threaded disengagement from the lower tie plate. Each washer member is manufactured from a spring material and includes at least one and preferably two radially protruding tangs T. These tangs are elongate and bent in an inverted U-shaped configuration. The inverted U-shaped configuration commences at the washer member and extends upwardly and outwardly away from the hex bolt to be locked. Reversal of the spring member occurs at the end of the U with the spring member returning angularly back towards the tie rod. In the return toward the tie rod, a gradual inward slope defining a gathering surface between the tie rod and bolt on one hand and the U-shaped tang on the other hand is defined that the U-shaped tang. From the end of the gathering surface, the tang extends vertically downward in a position of spring interference with one of the flat sides of the hexagonal bolt holding the tie rod in place. When the tie rod washer is in place with the nut fastened, the tang prevents the bolt from turning responsive to vibration and upward force on the upper tie plate due to outflowing water and steam. In remote disassembly of the fuel bundle, the gathering surface permits the tang to be biased away from the sides of the bolt by a specialized socket that penetrates interstitially between the lock washer and nut and captures the nut when it is unscrewed. The lock washer because of its spring action returns to its initial shape after the socket and nut are removed. In contrast to the prior art lock washer, the lock washer tangs strains and deformations are elastic. The possibility of tang breakage is eliminated and the lock washers can be reused.

Spring lock washer for tie rod nuts

In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between slender spring members and laterally oriented rigid stops.

Method of mounting a continuous loop spring on a nuclear fuel spacer

In a nuclear fuel assembly spacer providing passages for fuel rods or other elongated elements, a spring component of H-shape including a pair of spaced spring members of hairpin-like configuration connected by a retaining strap wherein an arched side of one of the spring members projects into one of the passages and the arched side of the other of the spring members projects into an adjacent one of the passages for resilient engagement with the fuel rods or other elongated elements extending through the passages.

Nuclear fuel assembly spacer and spring component therefor

A spacer for use in a fuel assembly of a nuclear reactor having thin, full-height divider members, slender spring members and laterally oriented rigid stops and wherein the total amount of spacer material, the amount of high neutron cross section material, the projected area of the spacer structure and changes in cross section area of the spacer structure are minimized whereby neutron absorption by the spacer and coolant flow resistance through the spacer are minimized.

Growing community of inventors

San Jose, CA, United States of America

Michael V Curulla