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

Method for purifying plutonium hexafluoride

Patent ·
OSTI ID:5768016

An effective method for purifying plutonium hexafluoride for the reprocessing of the spent nuclear fuel or for the recovery of fuel plutonium from the scrap by fluoride-volatility with high decontamination factors is presented using a selective adsorption of the fission products fluorides by letting the gas mixture flow through a layer of an adsorbent consisting of one or more of the specified compounds selected from hexafluoro sodium aluminate, zinc fluoride, nickel fluoride and ferric fluoride at an elevated temperature. The principle of the purification method is based on the fact that the fluorides of the fission products are easily adsorbed by the adsorbent but little plutonium hexafluoride is adsorbed. The fluorides of the fission products are easily removed from the adsorbent by heating and the recycling use of the adsorbent is possible.

Assignee:
Japan Atomic Energy Research Inst.
Patent Number(s):
US 4172114
OSTI ID:
5768016
Country of Publication:
United States
Language:
English