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A PRELIMINARY STUDY OF MOLTEN SALT POWER REACTORS

By H.G. MacPherson, L.G. Alexander, D.A. Carrison, J.Y. Estabrook, B.W. Kinyon, L.A. Mann, J.T. Roberts, F.E. Romie and F.C. VonderLage

Abstract

A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be the most resistant to corrosion. To study the performance, safety, economics, and construction costs of a typical molten salt reactor, a reactor of specific type and size was chosen for study. The reference design reactor was a two-region homogeneous converter with a core salt of 70 mole% Li/sup 7/F and 30% BeF/sub 2. ThF/sub 4/ and enough VF/sub 4/ for criticality were added. Study in- dicated that a molten salt reactor would prcduce economical power, but the problem of developing a salt core and a container metal which would last for mamy years of operation needed further study. (M.C.G.

Topics: Reactor Technology, Conversion-- Criticality-- Economics-- Homogeneous Reactors-- Operation-- Performance-- Planning-- Reactor Core-- Reactor Safety-- Zones, Alkali Metals-- Aluminum Alloys-- Beryllium Compounds-- Beryllium Fluorides-- Chlorides-- Chromium Alloys-- Confinement-- Containment-- Corrosion-- Fluorides-- Fused Salt Fuel-- Inconel Alloys-- Lithium Fluorides-- Melting Points-- Mixing-- Molybdenum Alloys-- Nickel Alloys-- Reactors-- Stability-- Thorium Fluorides-- Titanium Alloys-- Uranium Fluorides-- Zirconium Compounds
Publisher: Oak Ridge National Laboratory
Year: 1957
DOI identifier: 10.2172/4183642
OAI identifier:
Provided by: UNT Digital Library
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