Combustion Engineering, Inc.

Westinghouse Electric Company LLC

Ce Nuclear Power LLC

Daniel A Peck

Donn Moore Matteson

Vincent M Callaghan

Clifford B Martin

William J Heilker

John P Cook

An array grid includes a plurality of interlocking elongate strips. The strips are structured and configured to provide sufficient lateral support for steam generator tubing while minimizing the risk of attack by stress corrosion cracking to the steam generator tubes.

Steam generator tube support grid array

A blowdown manifold for a nuclear power plant includes a main conduit section, at least one coolant exhaust conduit, and at least one fluidic device. The main conduit section is connected to a pressure relief system in the nuclear power plant. The coolant exhaust conduit has a first end coupled to the main conduit section and a second end extending into a receptacle. The fluidic device is in fluid communication with the main conduit and exhibits a lower flow resistance to air than to water and steam.

Blowdown manifold evacuator for nuclear power plants

An augmented cooling system for a CEDM in a nuclear reactor includes self actuated louvers or flap valve louvers which allow hot air from the head lift rig to vent and cooler ambient air to enter the rig in the event that pressure is lost for the forced cooled air which normally cools the CEDM.

Self-actuated louvers for venting a CEDM cooling system of a nuclear reactor and method of using the same

A drain system for a shutdown cooling system of a pressurized water reactor type of a nuclear power plant (10) has an increased flow rate in the drain pipe (28) and drain pump (33). The hot leg (18) connected drain pipe has a vaned vortex breaker (30) mounted therein between its connection with the hot leg (18) lower region and the drain pump (33). This minimizes vortex-created cavitation in the drain pump thereby permitting the increased flow rate.

Drain system for a nuclear power plant

A tank (18) forms a chamber having an upper and lower region. The tank (18) is in even elevation with a horizontal pipe (12) having a top region and a bottom region. An upper connecting pipe (14) fluidly connects the top region of the pipe (12) to the upper region of tank (18). A lower connecting pipe (16) fluidly connects the bottom region of pipe (12) to the lower region of the tank (18). Heat junction thermocouples (22) generate a signal indicative of water in the pipe (12). The signal is transmitted to a remote location by line (24).

Midloop water level monitor

Means and method are disclosed for determining the fluid content within a large pressure vessel (12), without penetrating the vessel. Strain gauges (60) are located at the weight-bearing support structures (24) of the vessel, whereby calibrated differences in the weight of the empty vessel and the vessel as measured during operation gives a direct indication of fluid content. Preferably, the strain gauges (60) are associated with strain amplification elements (80) or shims, which are interposed between mating surfaces of the vessel support (24) and its base (44). The stress amplification element (80) has a smaller area of contact with the support member (24) than with the base (44), providing an effective higher coefficient of elasticity than that of the support member. In one embodiment, the strain gauge (60) is connected to a bolt (64) which tightly secures the vessel support (24) to its base (44).

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South Windsor, CT, United States of America

Daniel A Peck