LIQUID METAL FUEL TECHNOLOGY

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4260476

Frost, B R.T.; Addison, C C; Chitty, A; Geach, G A; Gross, P; James, J A; Metcalfe, G J; Raine, T; Sloman, H A

The work carried out at a number of laboratories on the metallurgical problems associated with the development of liquid metal fuelled reactors is outlined. The major effort has been concerned with a circulating fuel thermal system which employs a fuel of uranium dissolved in bismuth and a thorium-bismuth slurry blanket. However, a considerable amount of work has been done on a fast reactor concept. The development of suitable fuels has called for extensive work on solutions and suspensions of uranium and plutonium and their compounds in liquid metals. This has included the determination of solubility/temperature curves, the identification of intermetallic compounds, the measurement of thermodynamic activities, and the study of particle growth in suspensions or slurries. (auth)

• Research Organization: Atomic Energy Research Establishment, Harwell, Berks, Eng.; Univ. of Nottingham; General Electric Co., Ltd., Wembley, Eng.; Assoc. Electrical Industries, Ltd., Aldermaston, Berks, Eng.; Fulmer Research Inst., Stoke Poges, Eng.; British Thompson Houston Co., Ltd., Rugby, Eng.; Metcalfe (Hawker-Siddeley Nuclear Power Co., Ltd., Langley, Eng.; Metropolitan-Vickers Electrical Co., Ltd.,
• NSA Number: NSA-13-006779
• OSTI ID: 4260476
• Report Number(s): A/CONF.15/P/270
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BISMUTH ALLOYS
BLANKETS
EXPANSION
FAST FISSION FACTOR
INTERMETALLIC COMPOUNDS
LIQUID METAL FUEL
MEASURED VALUES
METALLURGY AND CERAMICS
PARTICLES
PHASE DIAGRAMS
PLUTONIUM
QUANTITATIVE ANALYSIS
REACTORS
SLURRIES
SOLUBILITY
SUSPENSIONS
THERMODYNAMICS
THORIUM ALLOYS
URANIUM
URANIUM ALLOYS
URANIUM COMPOUNDS