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Preparing Plutonium Metal via the Chloride Process

Journal Article · · Industrial and Engineering Chemistry
DOI:https://doi.org/10.1021/ie50618a027· OSTI ID:4000031

The chloride process was developed to decrease personnel exposure from the high neutron flux of plutonium fluorides. Neutron radiation from PuCl₃ measured 1/64th that from PuF₄. In continuous operation the plutonium was precipitated as oxalate, filtered, calcined at 300 deg C to oxide, then chlorinated with phosgene at 500 deg C. The chlorination rate was 250 grams of plutonium per hour. The PuCl₃ was reduced by calcium in heated pressure vessels. Yields were 97% as pure plutonium metal solidified as buttons in the bottom of the reusable crucibles. Plutonium-bearing dusts were filtered from the chlorinator off-gas stream by heated ceramic filters. Chloride powders did not hydrate in the dry atmosphere of dew point --20 deg C. Corrosion was controlled by dry atmosphere and by use of selected plastics and metals. (auth)

Research Organization:
General Electric Co., Richland, Wash.
Sponsoring Organization:
USDOE
NSA Number:
NSA-15-019756
OSTI ID:
4000031
Report Number(s):
HW-66128; HW-SA-1969; 0019-7866
Journal Information:
Industrial and Engineering Chemistry, Journal Name: Industrial and Engineering Chemistry Journal Issue: 6 Vol. 53; ISSN 0019-7866
Country of Publication:
Country unknown/Code not available
Language:
English