Siemens Power Corporation, Inc.

Advanced Nuclear Fuels Corporation

Exxon Nuclear Company, Inc.

Jack Yates

John F Patterson

Richard H Ewing

George C Cooke

Charles A Brown

Harold E Williamson

Trond A Bjornard

Robert B Macduff

Roger L Braaten

Peter P King

Wayne A VonOlnhausen

The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly. A coolant diverter is positioned in a spacer of a nuclear fuel rod assembly in the large subchannel above a part length fuel rod for increasing the hydraulic resistance of the large subchannel and for separating liquid from two phase flow.

Nuclear fuel rod assembly apparatus

A reactor coolant debris filter for insertion within a nuclear fuel assembly support.

Boiling water reactor fuel assembly filter

An improved fuel rod is provided having a part-length fuel rod portion that improves performance with respect to typical part-length fuel rods without significant degradation of the benefits that are achieved by using such a system, e.g., improved fuel utilization, stability, and shut down margin. The present invention provides a fuel rod for a light water nuclear reactors that comprises a part-length fuel rod and an extension tube having at least one wall member defining an enclosed flow path therethrough, the extension tube being coupled to a portion of the part-length fuel rod so as to be disposed axially above the part-length fuel rod, and including at least one inlet opening, for allowing fluid that surrounds the rod and initially comprises a two phase mixture of steam and liquid, to enter the enclosed fluid path and at least one outlet opening located above the inlet opening, the extension tube includes means for separating at least some of the steam located in the fluid from the liquid located therein. The improved fuel rod allows steam to bypass the upper active portions of the fuel assembly. A nuclear fuel rod for a light water reactor having a part length fuel rod and a reflex upper end fitting which functions to separate the liquid and vapor steam portions of two phase flow.

Coolant vent fuel rod and part length fuel rod having a reflex upper end

An arrangement for supporting a fuel assembly of a nuclear reactor has upper and lower reactor core support plates, upper and lower tie plates for supporting fuel rods and a coolant path through the assembly. The improvement comprises a redesigned lower tie plate for providing an upward biasing force to the assembly for forcing the upper tie plate against the upper reactor core support plate. The biasing force is in the same direction as a levitation force caused by coolant flow through the assembly. In a preferred form, the tie plate includes an upper and lower section with hold-up springs disposed between the two sections.

Non-levitating PWR fuel assembly

An instrument thimble tube shroud is disclosed which has a central cup surrounding an instrument thimble tube to prevent fluid flow about the thimble tube from causing excessive vibration and wear. A plurality of arms extend radially from the cup and have locking pads disposed at the end of each arm, springs extending from the pads engaging recesses in an adjacent fuel assembly nozzle to lock the shroud in position and prevent movement of the shroud or rotation due to aggressive fluid flow. Utilizing the inventive shroud prevents vibration and damage to the instrument thimble tube passing therethrough, enhancing life of the instrumentation and allowing continued observation of dynamics within a nuclear reactor.

Instrument thimble tube shroud

A debris screen for a fuel assembly for a reactor to which coolant fluid is supplied comprises a substantially planar plate member having an array of coollant openings extending through the plate member dimensioned to trap at least a portion of debris particles carried by the coolant; and a skirt member enclosing the periphery of the plate member; each of the coolant flow openings having a coolant entry region at a lower surface, a coolant exit region at an upper surface and a coolant flow path extending between the entry and exit regions, the flow path including an intermediate segment laterally offset from the entry and exit regions to cause coolant to change direction of flow in the intermediate segment and thereby prevent at least a portion of the debris particles from passing through the plate members.

Fuel assembly debris screen

An intermediate mixing grid for nuclear reactor fuel assemblies is made without the usual perimeter strip. The ends of the grid members are formed so that they hold the fuel rods at the edges of the assembly in place.

Intermediate mixing grid

A marked reduction in the pressure drop of cooling liquid through a grid spacer of a nuclear fuel assembly is attained by convexly contouring the upstream (usually the lower) edges of the grid members. Preferably, they are made streamlined or semicylindrical. This can be done by first beveling and then etching them, by directing a stream of mixture of abrasive and an organic polymer against them, or by traversing an electron or laser beam along them at a power and velocity such as to cause local melting. A lesser improvement is secured by beveling alone. A still further improvement can be obtained by also tapering the downstream (usually upper) edges.

Grid spacer and method of making same

A grid for use in nuclear fuel assemblies is made up of double grid members which are deformed so as to provide channels for the coolant. At least the upper portions of these channels are inclined relative to the axes of the fuel rods and are disposed in such a manner as to cause circulation of fluid about each individual rod and within the assembly. In one embodiment the grid is positioned between the positioning grids and serves primarily as a coolant deflector. In another embodiment so constructed as to serve the positioning grid, as well as a flow deflector, the channels are straight in their lower portions i.e. parallel to the axes of the fuel rods. In their upper portions they curve to provide the desired deflection of the cooling fluid and the straight sections have a slight bow outward, relative to the plane of the grid member of which they are a part. This outwardly bowed portion engages the fuel rod and acts as a positioning spring. The grid members are cut away adjacent the straight sections to give the necessary flexibility. This design is particularly useful in pressurized water reactors. In grids intended for use in boiling water reactors, where the lateral loading is less severe, the straight portion can be omitted. The two plates may be welded together at their intersections, at their upper edges only, while the lower edges are left free. In this case, the flexing of the grid members themselves serves to provide the spring forces necessary to position the fuel rods. In order to give improved flexibility, and proper fit with the rods when loaded, the surfaces of the channels which contact the fuel rods are given a twisted or helical formation.

Mixing grid

This invention is directed to a fuel assembly for boiling water reactors incorporating an advanced type of 'water rod.'

Growing community of inventors

Richland, WA, United States of America

Jack Yates