Primary system design studies for advanced direct cycle nuclear gas turbine plant
Continuing studies of the Gas Turbine High-Temperature Gas-Cooled Reactor (GT-HTGR) power plant have been directed toward identification of a plant configuration with improved economic incentives over competing electric power plants. This paper outlines the studies which led to the selection of the primary system for a plant with optimized parameters from the standpoint of minimum power generating cost. As in previously reported designs, an integrated type of plant embodying multiple helium gas turbine loops was selected. The layout of the power conversion loop (PCL) components in the prestressed concrete reactor vessel (PCRV) and the development of the primary system helium gas flow paths are discussed. Some of the preliminary design considerations for the turbomachinery, heat exchangers, thermal barrier, and control valves together with maintenance considerations are discussed. The reference plant preliminary design presented is based on a 3000-MW(t) core thermal rating with a reactor outlet (turbine inlet) temperature of 850/sup 0/C: the overall plant efficiency of the dry-cooled direct cycle nuclear gas turbine is 40 percent.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- EY-76-C-03-0167-046
- OSTI ID:
- 7312379
- Report Number(s):
- GA-A-14148; CONF-770317-1; TRN: 77-011262
- Resource Relation:
- Conference: 22. ASME international turbine conference, Philadelphia, PA, USA, 27 Mar 1977
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
GAS TURBINES
DESIGN
HEAT EXCHANGERS
HTGR TYPE REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
VALVES
ECONOMICS
EFFICIENCY
POWER GENERATION
REACTOR MAINTENANCE
CONTAINERS
CONTROL EQUIPMENT
COOLING SYSTEMS
EQUIPMENT
FLOW REGULATORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MAINTENANCE
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
TURBINES
TURBOMACHINERY
210300* - Power Reactors
Nonbreeding
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