STEAM-COOLED POWER REACTOR EVALUATION GRAPHITE-MODERATED, BOILING WATER, STEAM SUPERHEAT REACTOR. VOLUMES I AND II

Technical Report · Fri Sep 01 00:00:00 EDT 1961

OSTI ID:4834796

A conceptual reference design of a 318-Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described. In this concept, the coolant is light-water-andsteam in pressure tubes which pass through the graphite moderator. Fuel slugs of uranium carbide in a graphite matrix are in channels in the moderator, separated from the coolant by the graphite. The reactor is designed for refueling under load and for direct mdintenance. Turbine throttle steam conditions are 1800 psig/1000 deg F with 1000 deg F reheat which yields a net cycle efficiency of 41.8%. Descriptions of the design of the reactor core, fuel handling system, control rod and drive system, piping system, control and instrumentation system, auxiliary reactor equipment systems, electrical systems, and the reactor plant facilities are included. In addition, the plant operation is described during normal and abnormal operating conditions. A discussion of potential cost savings and a description of the required research and development are presented. (auth)

• Research Organization: Atomics International.Div. of North American Aviation, Inc., Canoga Park, Calif.
• NSA Number: NSA-15-030258
• OSTI ID: 4834796
• Report Number(s): NAA-SR-6100(Vols.I and II)
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
CONFIGURATION
CONTROL SYSTEMS
COOLANT LOOPS
ECONOMICS
EFFICIENCY
ELECTRICITY
FUEL ELEMENTS
GRAPHITE MODERATOR
HIGH TEMPERATURE
INSTRUMENTS
MAINTENANCE
OPERATION
PIPES
PLANNING
POWER PLANTS
PRESSURE
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
REMOTE HANDLING
STEAM
SUPERHEATING
TUBES
TURBINES
URANIUM CARBIDES
WATER COOLANT