HALLAM NUCLEAR POWER FACILITY PROTOTYPE FOR ADVANCED SODIUM-COOLED POWER STATIONS

Journal Article · Thu Feb 01 04:00:00 EST 1962 · Power App. Systems

OSTI ID:4745388

Dickinson, R W; Gerber, R C; Larson, C L

The sodium-cooled graphite-moderated nuclear reactor concept is described. The Hallam Nuclear Power Facility (HNPF) for producing superheated steam to generate 75 Mwe net power represents a step toward the ultimate capabilities of this concept. A larger plant design, capable of 360 Mwe gross output, is also presented. The advanced design is expected to produce steam thermodynamically comparable to steam plants that are economically competitive with fossil-fuxled stations in many areas of the United States. Two important characteristics of the sodium-cooled reactor concept are the excellent heat transfer properties of liquid sodium and the inherent safety of a low-pressure reactor system. These characteristics are utilized extensively in this concept to minimize total power cost. (auth)

• Research Organization: north American Aviation, Inc. Canoga Park, Calif.
• NSA Number: NSA-17-007622
• OSTI ID: 4745388
• Journal Information: Power App. Systems, Journal Name: Power App. Systems Vol. Vol: No. 58
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

COAL
ECONOMICS
EFFICIENCY
ELECTRICITY
ELECTRONS
FUELS
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
HNPF
IONS
LIQUID METAL COOLANT
MAGNETIC FIELDS
OILS
PLANNING
PLASMA
POWER PLANTS
PRESSURE
PRODUCTION
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
SHOCK WAVES
SODIUM
STEAM
SUPERHEATING
TEMPERATURE
THERMODYNAMICS