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U.S. Department of Energy
Office of Scientific and Technical Information

LIQUID METAL FUEL REACTOR EXPERIMENT. ANNUAL TECHNICAL REPORT

Technical Report ·
OSTI ID:4222349
LMFRE-I Desin: A detailed design description is given of a 5-Mw, Bi-U fueled, graphite moderated reactor. Studies of reactor hazards. reactor mathematics and physics, systems arrangements, remote maintenance, fuel chemistry, and site and building development are included. Research and Development: Corrosion loop studies designed to demonstrate the feasibility of using Croloy as a structural material are reviewed. Progress in the development of liquid metal control elements is outlined. Equipment and procedures developed for welding beryllium are described. The mechanical properties of plain and sawtooth cemented joints in graphite were determined. Preliminary feasibility studies of impregnating reactor graphite with various metals to prevent bismuth absorption are described. The preparation methods and some of the properties of Bi-ThO/sub 2/ slurries are given. The solubility of U in liquid Bl-U alloy is plotted as a function of temperature. The effects of fission products, Zr, Mg, and Na contamination on U solubility are also given. Techniques for decontaminating Croloy, using mercury and mercury vapor, were evaluated. Croloy bellows and valves were tested in liquid Bi; results are summarized. Standard and modified remote handling and remote viewing equipment for use in the LMFRE-I facility is described. (D.E.B.)
Research Organization:
Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
NSA Number:
NSA-14-002200
OSTI ID:
4222349
Report Number(s):
BAW-1136
Country of Publication:
United States
Language:
English