General Electric Company

Global Nuclear Fuel - Americas, LLC

Johnny R Skipper

David Grey Smith

Michael T Kiernan

Robert A Haughton

Carlton Wayne Clark

Paul Everett Cantonwine

Jaime A Zuloaga, Jr

Andrew K Langston

Ralph J Reda

Andrew A Lingenfelter

Alexander Michael Hay

Charles B Patterson, Jr

John L Harmon

Edward G Apple

Jeffrey P Johnson

Robert J Sziemkiewicz

Harry L Batson

James M Gehr

A method to confine a nuclear reactor fuel bundle assembly including: inserting a lower portion of the fuel bundle assembly into an open end of a lower fuel particle barrier; supporting the lower portion of the fuel bundle with the lower fuel particle barrier; grasping the lower portion of the fuel bundle assembly with the lower fuel particle barrier; lowering an upper fuel particle barrier over an upper tie plate of the fuel bundle assembly; moving at least a portion of a handle fixed to the upper tie plate through an open slot in the upper fuel particle barrier; closing the open slot with a closure device after the handle passes through the slot, and preventing fuel particles being released from the nuclear reactor fuel bundle assembly by the upper and lower fuel particle barriers.

Channel confinement method for dry-storage of BWR fuel bundles

A nuclear reactor fuel bundle confinement system including: a fuel bundle with an upper tie plate; a channel enclosing the fuel bundle; a handle for the fuel bundle extending above the fuel bundle; an upper fuel particle barrier positioned over the upper tie plate and above the fuel rods, wherein the fuel particle barrier has a permeable panel at least co-extensive with an open area of the upper tie plate; a slot in the permeable panel through which passes the handle, and a closure device on the fuel particle barrier having a closed position which covers the slot and an open position that leaves the slot open; a lower fuel particle barrier positioned over the lower tie plate and below the fuel rods, wherein the lower portion of the fuel bundle assembly is grasped by the lower fuel particle barrier.

Channel confinement system and method for dry-storage of BWR fuel bundles

A high pressure laser welding method and apparatus enables seam welding of a nuclear fuel rod at hyperbaric pressure. In an automatic process, a loaded fuel rod and an upper end plug are mated within a sealable weld box. A pressure within the weld box is controlled relative to a pressure within the fuel rod, and a laser assembly welds the seam at hyperbaric pressure. Helium flowing through a laser window nozzle during welding prevents soot contamination of the laser window glass and prevents formation of ionic plasma. The upper end plug fuel rod welding operation is thus reduced to a single step and eliminates inspection related tasks with respect to a sealed hole.

High pressure laser welding of nuclear fuel rods

A TIG welding system for controlling the weld shape for the seal welding of a small pressurization hole in the end plug of nuclear fuel rods. The controlled shape of the seal weld enables improved ultrasonic detection capabilities. The system achieves the desired weld shape by controlling the pressure differential between the interior and exterior volumes of the fuel rod. The weld box pressure is decreased in accordance with Boyle's law while the weld material for sealing the hole is molten. The system uses an output from the weld electronics as an input to a programmable logic controller ('PLC'). After a programmed time delay, the PLC outputs a signal to a solenoid valve to open a 'ballast' volume. The expansion of gas from the weld box into the ballast volume causes a sudden drop in pressure to a level below the pressure inside the fuel rod. As a result of this pressure differential, the molten weld material forms a concave weld upon solidification.

Weld shape control system for TIG welding of small pressurization hole

Nuclear fuel rod having concave weld across pressurization hole in end

To inspect the integrity of pressurization holes in nuclear fuel rod final end plugs, quality assurance apparatus includes an adapter providing a test chamber into which an end plug is inserted. Instrument gas is introduced into the test chamber through an inlet port for flow to the atmosphere through the pressurization hole. A mass flow meter measures the gas flow through the pressurization hole to determine if it is capable of supporting requisite pressurization of a nuclear fuel rod when the end plug is assembled thereto.

Nuclear fuel rod end plug pressurization hole inspection apparatus

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Leland, NC, United States of America

Johnny R Skipper