Ga Technologies, Inc.

Other

The United States of America As Represented by the United States

General Atomics, Inc.

Abitibi-price, Inc.

Abitibi Consolidated Inc.

Stanley L Koutz

Philip Whiting

Kevin William Downey

David A Hazlebeck

Luke David Bond

Charles Cheslay Mills

Davorin D Kapich

Leonardo Cavallaro

Luke D Bond

Charles C Mills

Charles O Peinado

David Alan Hazlebeck

A supercritical water oxidation reactor is alternately supplied with a feed stream and a flushing stream. The feed stream contains organic and inorganic materials. The organic materials are oxidized under supercritical conditions in the reactor and the inorganic materials precipitate out of solution under the same conditions. The flushing stream is a solution in which the inorganic material is soluble. More than one supercritical water oxidation reactor may be connected so that the feed stream is alternately supplied to each reactor. During the period when the feed stream is being supplied to a reactor the effluent from the reactor is cooled to a temperature at which inorganic precipitates are soluble and is then supplied as a flushing stream to one or more of the remaining connected supercritical water oxidation reactors.

Method and apparatus to remove inorganic scale from a supercritical

Apparatus to remove inorganic scale from a supercritical water oxidation

Method to remove inorganic scale from a supercritical water oxidation

A nuclear reactor includes a core submerged in a pool of liquid. Under normal conditions, coolant flows through the core without intermixing with the liquid in the pool. In the event of failure of the primary coolant circulation system, liquid from the pool flows through openings in the primary circulation system so as to cool the core by natural convection. Flow through the openings during normal operating conditions may be controlled regardless of the flow rate.

Reactor with natural convection backup cooling system

A system for increasing the temperature of a fluid heated by a high temperature gas cooled nuclear reactor to a sufficient temperature to supply the heat of reaction for a high temperature chemical process. The system includes a secondary loop having a working fluid heated to a first temperature by the nuclear reactor, and has a heat pump connected in the secondary loop and adapted to increase and thereby augment the temperature of the working fluid in the secondary loop sufficiently to supply the heat of reaction for a high temperature chemical process such as in a reformer. The system also provides low temperature heat in the form of steam which may be used in a turbine to provide power to the compressor of the heat pump and for auxilliary apparatus.

Heat pump augmentation of nuclear process heat

A gas-cooled nuclear reactor includes a central core located in the lower portion of a prestressed concrete reactor vessel. Primary coolant gas flows upward through the core and into four overlying heat-exchangers wherein stream is generated. During normal operation, the return flow of coolant is between the core and the vessel sidewall to a pair of motor-driven circulators located at about the bottom of the concrete pressure vessel. The circulators repressurize the gas coolant and return it back to the core through passageways in the underlying core structure. If during emergency conditions the primary circulators are no longer functioning, the decay heat is effectively removed from the core by means of natural convection circulation. The hot gas rising through the core exits the top of the shroud of the heat-exchangers and flows radially outward to the sidewall of the concrete pressure vessel. A metal liner covers the entire inside concrete surfaces of the concrete pressure vessel, and cooling tubes are welded to the exterior or concrete side of the metal liner. The gas coolant is in direct contact with the interior surface of the metal liner and transfers its heat through the metal liner to the liquid coolant flowing through the cooling tubes. The cooler gas is more dense and creates a downward convection flow in the region between the core and the sidewall until it reaches the bottom of the concrete pressure vessel when it flows radially inward and up into the core for another pass. Water is forced to flow through the cooling tubes to absorb heat from the core at a sufficient rate to remove enough of the decay heat created in the core to prevent overheating of the core or the vessel.

Gas-cooled nuclear reactor

Growing community of inventors

San Diego, CA, United States of America

Stanley L Koutz