A process for converting impure plutonium dioxide (approx. 96% pure) to high-purity plutonium metal (>99.9%) was developed. The process consists of reducing the oxide to an impure plutonium metal intermediate with calcium metal in molten calcium chloride. The impure intermediate metal is cast into an anode and electrorefined to produce high-purity plutonium metal. The oxide reduction step is being done now on a 0.6-kg scale with the resulting yield being >99.5%. The electrorefining is being done on a 4.0-kg scale with the resulting yield being 80 to 85%. The purity of the product, which averages 99.98%, is essentially insensitive to the purity of the feed metal. The yield, however, is directly dependent on the chemical composition of the fe...
Batches of plutonium dioxide were chlorinated by reaction with phosgene or carbon tetrachloride. Plu...
The purpose of this report is to provide environmental data and reference process information associ...
"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-3118 ; UC-4, Chemistry ; TID-450...
The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce ...
Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in ...
Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic ma...
Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999 % of the organic m...
The recycle of plutonium from refractory residues is a necessary activity for the nuclear weapon pro...
Pyrochemical operations at Los Alamos Plutonium Facility (TA-55) use high temperature melt s of calc...
Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred ...
AbstractA pyrochemical process is developed to upgrade the safety of plutonium spent salts interim s...
The authors have developed two processes for the recovery of weapons grade Pu, as either Pu metal or...
The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact fac...
The usefulness of molten salt solutions of Cs2PuCl6 for plutonium electrolyzes has been investigated...
Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas thr...
Batches of plutonium dioxide were chlorinated by reaction with phosgene or carbon tetrachloride. Plu...
The purpose of this report is to provide environmental data and reference process information associ...
"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-3118 ; UC-4, Chemistry ; TID-450...
The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce ...
Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in ...
Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic ma...
Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999 % of the organic m...
The recycle of plutonium from refractory residues is a necessary activity for the nuclear weapon pro...
Pyrochemical operations at Los Alamos Plutonium Facility (TA-55) use high temperature melt s of calc...
Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred ...
AbstractA pyrochemical process is developed to upgrade the safety of plutonium spent salts interim s...
The authors have developed two processes for the recovery of weapons grade Pu, as either Pu metal or...
The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact fac...
The usefulness of molten salt solutions of Cs2PuCl6 for plutonium electrolyzes has been investigated...
Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas thr...
Batches of plutonium dioxide were chlorinated by reaction with phosgene or carbon tetrachloride. Plu...
The purpose of this report is to provide environmental data and reference process information associ...
"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-3118 ; UC-4, Chemistry ; TID-450...