Westinghouse Electric Corporation

The United States of America As Represented by the Department of Energy

U.S. Dept. of Energy

Noel P Grimm

Richard E Kothmann

Frank I Bauer

Robert S Mavretish

Thomas G Bengel

Robert B Salton

Phillip E Miller

James Sejvar

Raymond J Nath

Russell R Booth, Jr

Vaughn M Thomas

Abram Batenburg

A process for controlling the heating of a thin-walled body according to a predetermined temperature program by means of electrically controllable heaters, comprising: disposing the heaters adjacent one surface of the body such that each heater is in facing relation with a respective zone of the surface;

Menu driven heat treatment control of thin walled bodies

A temperature monitoring device for measuring the temperature at a surface of a body, composed of: at least one first thermocouple and a second thermocouple; support members supporting the thermocouples for placing the first thermocouple in contact with the body surface and for maintaining the second thermocouple at a defined spacing from the body surface; and a calculating circuit connected to the thermocouples for receiving individual signals each representative of the temperature reading produced by a respective one of the first and second thermocouples and for producing a corrected temperature signal having a value which represents the temperature of the body surface and is a function of the difference between the temperature reading produced by the first thermocouple and a selected fraction of the temperature reading provided by the second thermocouple.

Temperature monitoring device and thermocouple assembly therefor

A cylindrical coffer dam assembly is described for use in temporary shielding personnel from nuclear reactor stored internals' radiation. The coffer dam is made up of substantially equal segments small enough to pass through the equipment hatch of the reactor containment building. The segments are pre-fabricated at a factory, transported to the plant, introduced individually into the containment building, and assembled together in sealing relation at the operating floor into a complete coffer dam. The coffer dam is moved to the reactor vessel and connected to the reactor vessel upper flange in sealing relation. The coffer dam can be disconnected, disassembled, removed and re-used at other nuclear reactors.

Coffer dam for temporary shielding of reactor vessel internals

A first plurality of water filled shielding tanks is introduced through a nuclear reactor containment building hatch and placed between the stored core internals and the reactor vessel. A support structure for this vertical wall is previously shipped, disassembled, introduced into containment and erected between the reactor vessel and the stored internals. A second plurality of water filled shielding tanks is placed on the containment building operating floor level to cover the stored internals. Once in place, the tanks allow manned activity in the reactor vessel area, such as preparations for annealing. The method includes the steps of: removing the nuclear fuel from the reactor; storing both the upper and lower internals underwater; assembling the support structure and placing same in position in the refueling canal; introducing the vertical and horizontal tanks through the hatch; filling the vertical shielding tanks with water and placing same in the support structure; filling the horizontal shielding tanks with water and placing them above the stored internals and the vertical tanks; draining water from the refueling canal to the level of the reactor vessel flange; performing an operation requiring human intervention such as annealing; flooding the refueling canal to near the operating floor elevation; and decontaminating the tanks and support structure and removing same.

Method for temporary shielding of reactor vessel internals

Growing community of inventors

Monroeville, PA, United States of America

Noel P Grimm