A SODIUM COOLED, GRAPHITE MODERATED, LOW ENRICHMENT URANIUM REACTOR FOR THE PRODUCTION OF USEFUL POWER

Technical Report · Wed Sep 15 04:00:00 EDT 1954

DOI:https://doi.org/10.2172/4350786· OSTI ID:4350786

Weisner, E.F. ed.

A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)

• Research Organization: North American Aviation, Inc., Downey, Calif.
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-12-001085
• OSTI ID: 4350786
• Report Number(s): NAA-SR-1028
• Country of Publication: United States
• Language: English

Related Subjects

CONFIGURATION
COOLANT LOOPS
ECONOMICS
EFFICIENCY
ENRICHMENT
FUEL ELEMENTS
GENERATORS
GRAPHITE MODERATOR
HEAT EXCHANGERS
HEAT TRANSFER
HIGH TEMPERATURE
LIQUID METAL COOLANT
MECHANICAL STRUCTURES
PHYSICS
PLANNING
POWER PLANTS
PRESSURE
PRODUCTION
RADIOACTIVITY
REACTOR CORE
SODIUM
STANDARDS
STEAM
TEMPERATURE
TURBINES
URANIUM