Preparing Plutonium Metal via the Chloride Process
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
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PLUTONIUM TRICHLORIDE: PREPARATION BY REACTION WITH PHOSGENE OR CARBON TETRACHLORIDE, AND BOMB REDUCTION TO METAL
Related Subjects
CALCIUM
CERAMICS
CHLORINATION
CONTROL ELEMENTS
CORROSION
CRUCIBLES
DUSTS
FILTERS
HEATING
METALS
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON FLUX
OXALATES
PHOSGENE
PLUTONIUM CHLORIDES
PLUTONIUM COMPOUNDS
PLUTONIUM FLUORIDES
PLUTONIUM OXIDES
POLYMERS
POWDERS
PRECIPITATION
PRESSURE VESSELS
RADIATIONS
REDUCTION