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Title: Heat pump augmentation of nuclear process heat

A system is described for increasing the temperature of a working fluid heated by a nuclear reactor. The system consists of: a high temperature gas cooled nuclear reactor having a core and a primary cooling loop through which a coolant is circulated so as to undergo an increase in temperature, a closed secondary loop having a working fluid therein, the cooling and secondary loops having cooperative association with an intermediate heat exchanger adapted to effect transfer of heat from the coolant to the working fluid as the working fluid passes through the intermediate heat exchanger, a heat pump connected in the secondary loop and including a turbine and a compressor through which the working fluid passes so that the working fluid undergoes an increase in temperature as it passes through the compressor, a process loop including a process chamber adapted to receive a process fluid therein, the process chamber being connected in circuit with the secondary loop so as to receive the working fluid from the compressor and transfer heat from the working fluid to the process fluid, a heat exchanger for heating the working fluid connected to the process loop for receiving heat therefrom and for transferring heat tomore » the secondary loop prior to the working fluid passing through the compressor, the secondary loop being operative to pass the working fluid from the process chamber to the turbine so as to effect driving relation thereof, a steam generator operatively associated with the secondary loop so as to receive the working fluid from the turbine, and a steam loop having a feedwater supply and connected in circuit with the steam generator so that feedwater passing through the steam loop is heated by the steam generator, the steam loop being connected in circuit with the process chamber and adapted to pass steam to the process chamber with the process fluid.« less
Authors:
Publication Date:
OSTI Identifier:
5708192
Report Number(s):
US 4576783
Resource Type:
Patent
Resource Relation:
Patent File Date: Filed date 9 Oct 1984
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HEAT PUMPS; AUGMENTATION; HTGR TYPE REACTORS; PROCESS HEAT REACTORS; COMPRESSORS; COOLANTS; FEEDWATER; HEAT EXCHANGERS; HEAT TRANSFER; PRIMARY COOLANT CIRCUITS; PROCESS HEAT; REACTOR CORES; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TEMPERATURE EFFECTS; TURBINES; WORKING FLUIDS; BOILERS; COOLING SYSTEMS; ENERGY; ENERGY SYSTEMS; ENERGY TRANSFER; FLUIDS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT; HYDROGEN COMPOUNDS; MACHINERY; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TURBOMACHINERY; VAPOR GENERATORS; WATER 210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987); 210300 -- Power Reactors, Nonbreeding, Graphite Moderated