Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.

Abstract: 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.