A SODIUM-GRAPHITE REACTOR STEAM-ELECTRIC STATION FOR 75 MEGAWATTS NET GENERATION

Technical Report · Tue Mar 22 04:00:00 EST 1955

DOI:https://doi.org/10.2172/4350785· OSTI ID:4350785

Weisner, E F; Sybert, W M

The major design features, nuclear characteristics and performance data for a nuclear fueled central station power plant of 75,000 kw net capacity are presented. The heat source is a Na cooled graphite moderated reactor. The design of the reactor takes full advantage of the experience gained to date on the Sodium Reactor Experiment (SRE); the plant described here is a straightforward extension of the smaller experimental SRE, which is now under construction. The fuel elements are made up of rod clusters and the moderator is in the form of Zr canned graphite elements. The performance of the reactor has been based on conservative temperatures and coolant flow velocities which result in a plant with "built-in reserve." Thus, as experience is gained and anticipated improvements in reactor fuel elements and construction materials are proven, the performance of the plant can be increased accordingly. Two reactor designs are described, one for operation with slightly enriched U fuel elements and the other for operation with Th--U fuel elements. The associated heat exchangers, pumps, steam, and electrical generating equipment are identical for either reactor design. An analysis of turbine cycles describes the particular cycle chosen for initial operation and discusses a method by which modern central station performance can be initially obtained. The design and performance data which are required to enable reliable estimates of the plant construction and operating costs to be made are established. (auth)

• Research Organization: North American Aviation, Inc., Downey, Calif.
• Sponsoring Organization: USDOE
• NSA Number: NSA-12-001086
• OSTI ID: 4350785
• Report Number(s): NAA-SR-1300
• Country of Publication: United States
• Language: English

Related Subjects

CANNING
CONFIGURATION
COOLANT LOOPS
ECONOMICS
EFFICIENCY
ELECTRICITY
ENRICHMENT
FABRICATION
FUEL ELEMENTS
GENERATORS
GRAPHITE
GRAPHITE MODERATOR
HEAT EXCHANGERS
HEAT TRANSFER
HIGH TEMPERATURE
LIQUID FLOW
LIQUID METAL COOLANT
MECHANICAL STRUCTURES
MODERATORS
NEUTRON FLUX
OPERATION
PERFORMANCE
PHYSICS
PLANNING
POWER PLANTS
PRODUCTION
PUMPS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTORS
RODS
SODIUM
SRE
STABILITY
STEAM
TEMPERATURE
THORIUM
TRANSIENTS
TURBINES
URANIUM
VELOCITY
ZIRCONIUM