AN EVALUATION OF MERCURY COOLED BREEDER REACTORS
Author(s) -
J.O. Bradfute,
D.W. Battles,
G.S. Clark,
R.E. Corridan,
E.T. Gellenbeck,
D.L. Kavanagh,
D.R. Mash,
F. E. Romie,
R.H. Whitlock
Publication year - 1959
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4170077
Subject(s) - breeder (animal) , mercury (programming language) , nuclear engineering , authorization , breeder reactor , coolant , environmental science , boiling , engineering , waste management , computer science , blanket , physics , mechanical engineering , materials science , computer security , programming language , composite material , thermodynamics
Under the New Reactor Concepts Evaluation Program sponsored by the United States Atomic Energy Commission. Advanced Technology Laboratories (a Division of American Radiator & Standard Sanitary Corporation) has undertaken am investigation of the technical feasibility and economic potential of the use of boiling mercury as a coolant for fast breeder reactors The investigation was performed between January 1, 1959, and October 31. 1959. This is the final report on that investigation and is submitted in compliance with the terms of the program authorization, Contract Number AT(04-3)-109, Project Agreement Number 4. (auth
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