Westinghouse Electric Corporation

Arnold H Redding

Stephen N Tower

John A George

Paul Cohen

Removal of concentrated suspended particulate material from the recirculating carry-over water in a nuclear steam generator is provided by establishing a mud drum or reservoir of relatively quiescent water, permitting the concentrated solids contained therein to settle out prior to returning the water for mixing with the feedwater. Baffles in the mud drum intercept the entering carry-over water in a manner such that only a small portion of it is exchanged by the newly entering water so that, for the most part, there is sufficient residence time in a relatively quiescent environment to settle out the solids.

Sludge collection system for a nuclear steam generator

An improved thermal power plant and method of power generation which minimizes thermal stress and chemical impurity buildup in the vaporizing component, particularly beneficial under loss of normal feed fluid and startup conditions. The invention is particularly applicable to a liquid metal fast breeder reactor plant.

Apparatus and method for thermal power generation

A core cooling system for a nuclear reactor having a plurality of primary fluid flow systems. The reactor coolant flow from the primary systems is joined upon entering the pressure vessel. Jointure is accomplished in a common chamber causing high coolant flow velocities at low static pressures. If a pipe ruptures in one of the primary fluid flow systems, the low pressure in the common chamber minimizes leakage from the intact flow systems. This allows continuation of coolant flow through the nuclear core for a sufficient length of time to effectively eliminate the possibility of thermal damage.

Nuclear reactor core cooling arrangement

A core cooling system is disclosed for a nuclear reactor of the type utilizing a liquid coolant with a cover gas above free surfaces of the coolant. The disclosed system provides for a large inventory of reactor coolant and a balanced low pressure cover gas arrangement. A flow restricting device disposed within a reactor vessel achieves a pressure of the cover gas in the reactor vessel lower than the pressure of the reactor coolant in the vessel. The low gas pressure is maintained over all free surfaces of the coolant in the cooling system including a coolant reservoir tank. Reactor coolant stored in the reservoir tank allows for the large reactor coolant inventory provided by this invention.

Growing community of inventors

Export, PA, United States of America

Arnold H Redding