Thomas L Rohosky

46997539, Oct 13, 1987

Mar 27, 1986

6/845303

Thomas L. Rohosky - West Mifflin PA
Kenneth J. Swidwa - N. Versailles PA

Westinghouse Electric Corp. - Pittsburgh PA

G21C 1900

376268

The responses of a nuclear reactor refueling machine to commands from a detachable control console are simulated to allow operation of the console for testing and operator training with the console removed from the machine. A simulator, which is connected to the console by the same input and output leads which normally connect the console to the refueling machine, includes a single pulse generator driven by a single three phase A-C motor to simulate movement of the refueling machine bridge, trolley and hoist. The motor drive signals generated on separate console output leads are all connected to the single simulator motor, while the brake release signals energize relays which switch the pulse signals generated by the single pulse generator to the console input leads corresponding to the selected refueling machine component drive motor. The portable simulator also contains relays which simulate engagement and disengagement of fuel assembly and control rod cluster grippers and a device for coupling portions of the refueling machine mast to the hoist. In addition, a number of circuits are provided for testing various control console functions.

48948497, Jan 16, 1990

Sep 30, 1988

7/252218

Thomas L. Rohosky - West Mifflin PA
Kenneth J. Swidwa - N. Versailles PA
James R. Marshall - Penn Hills PA

Westinghouse Electric Corp. - Pittsburgh PA

G21C 1910

376268

A system for transferring fuel assemblies in a nuclear reactor includes a load control system which compares the current load to the more restrictive of fixed overload and underload limits, and instantaneous overload and underload limits continuously calculated from a running average of the measured load. Operation of the refueling machine is terminated if any of these limits are exceeded. The system also accommdates for changes in buoyancy and tension loading applied by spring loaded reels for pneumatic hoses and electrical cables servicing the gripper which engages the fuel assembly as the mast supporting the fuel assembly is raised and lowered in the pool of shielding water covering the reactor core. The current and recent suspended load measurements are displayed relative to the fixed and instantaneous overload and underload limits on a graphic display along with speed and other pertinent data.