Westinghouse Electric Company LLC

Combustion Engineering, Inc.

Bruce F Allen

Gregory E Falvo

Alexander W Harkness

Edward F Lamoureux

David L Crick

Alfred D DePeau

Brian W Ring

Brian P Coombs

A magnetic jack control rod drive rod drive system having the magnetic coils that operate the moving parts of the drive system wound from anodized aluminum magnet wire or ceramic coated nickel clad copper and enclosed within a hermetically sealed housing that is pressurized with helium.

Nuclear reactor internal electric control rod drive mechanism assembly

A control rod drive system for a nuclear reactor that employs hydraulic cylinders to operate a conventional plunger/gripper drive system to incrementally move control rods into and out of the core of a reactor. The pressure differential for driving hydraulic pistons within the cylinders is obtained from the difference in pressure between the outside and inside of the core barrel of the reactor and control of the pistons is obtained from external solenoids attached to the reactor control system. The external solenoids regulate a charging pump feed to Poppet valves that control the hydraulic feed to the cylinders. A hydraulic piston/cylinder drive is also provided for the shutdown rods which operate in either an all in or out of the core condition.

Nuclear reactor internal hydraulic control rod drive mechanism assembly

Anchor assembly apparatus for improving the structural integrity of a guide tube ( ) in a nuclear fuel bundle ( ). A sleeve ( ) has a proximate end ( ) and a distal end ( ) that is adapted for insertion into a receiving end ( ) of the guide tube. A pin ( ) has a near end ( ) and a far end ( ) adapted for insertion into the sleeve at the sleeve's proximate end. The pin has an external surface ( ) that applies a radial force to an inner surface ( ) of the sleeve when the pin is inserted into the sleeve. The force is sufficient to cause a locking surface ( ) on the sleeve to expand radially outward.

Anchor assembly for fuel bundle

An apparatus for hydrostatic pressure testing of tubular products that enables short segments of the tubular product to be individually tested under conditions simulating a capped tube hydrostatic test. The apparatus includes a first seal bladder and gripper member assembly connected to a second seal bladder and gripper member assembly by a connecting member that allows relative axial movement between the two assemblies. A fluid outlet port is provided in the connecting member to introduce pressurized fluid into the short segment of the tubular product between the seal bladders of the two assemblies. Since the first seal bladder and gripper member assembly is axially movable relative to the second seal bladder and gripper member assembly, an axial stress as well as a hoop stress will be induced in the tubular product during testing.

Apparatus for hydrostatic pressure testing of tubular products

A vent tube (66) and housing nut (62) replace the original housing plug (52) on a pressurized water nuclear reactor. The vent tube engages the installed vent stem (38) cross-slot (48) with a cross-shaped projection (70). During operation, the vent tube (66) is pushed down to engage the vent stem (38) and rotated to allow vented air to travel through stem (38) and tube (66). After venting, the vent stem is rotated back and tightened. The invention provides visual indication of a leaking ball (32) since any leakage lifts vent tube (66). Time required for venting is reduced and no removal of installed ball seal (32,34), a proven primary seal, is required.

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Granby, CT, United States of America

Bruce F Allen