A STUDY OF WET STEAM AS A REACTOR COOLANT. Joint Summary Report covering Period October 1, 1959-May 31, 1961

Technical Report · Sun Sep 10 04:00:00 EDT 1961

OSTI ID:4826365

Wet steam under dispersed flow conditions (fog or spray flow) was studied as a coolant for nuclear power reactors. The work accomplished included extensive heat transfer and hydrodynamics measurements, corrosion and erosion tests under aggravated conditions, exploration of means for efficient coolant mixing and separation, and theoretical examination of the experimental data. A preliminary design of a 300 Mw(e) light water-moderated reactor, using wet steam under fog flow conditions as the coolant, indicated a power generation cost in the range of 6.5 mills/kwh and a capital cost of about 0/kw(e), estimated on the basis of USAEC technical and economic ground rules used in conjunction with the recently concluded Steam-Cooled Power Reactor Evaluation. Improved operational nuclear safety characteristics are indicated over boiling water reactor systems. (auth)

• Research Organization: Centro Informazioni Studi Esperienze, Milan; Ansaldo S.p.A., Genoa; and United Nuclear Corp. Development Div., White Plains, N.Y.
• NSA Number: NSA-16-003942
• OSTI ID: 4826365
• Report Number(s): NDA-2132-6; CISE-R-44
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
COOLANT LOOPS
COOLANTS
CORROSION
ECONOMICS
EFFICIENCY
EROSION
GAS COOLANT
GAS FLOW
HEAT TRANSFER
HUMIDITY
MATERIALS TESTING
MEASURED VALUES
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
STANDARDS
STEAM
THERMODYNAMICS
WATER COOLANT
WATER MODERATOR