Reprocessing of the ARE fuel was resumed after extensive leak testing in the pilot plant. This was considered necessary to assure no recurrence of gaseous UF/sub 6/ leaks as experienced in Run E-2. In the four additional runs required to complete the program, about 641 kg of fluoride salt containing 40.64 kg of fully enriched uranium was reprocessed. Recovery as UF/sub 6/ product represented 97.97% of the feed, with 0.01% measured losses. An additional 2.14% was reclaimed from NaF beds. The product was of sufficient purity to meet specifications for material designated for reduction to uranium metal. Decontamination from fission products was essentially complete. Calculations based on the entire ARE program indicated 96.38% product recovery...
Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material proper...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot pl...
After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations ...
As part of a continuing program on the development of fluid-bed fluoride volatility processes, metho...
8 2 5 6 7 6 1 1 B 3 7 3 7 reprocessing scheme which may be applicable to most power reactor fuels is...
A preliminary chemical flowsheet is presented of a fluoride volatility process for recovering and de...
The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 k...
The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 k...
For nearly four decades, the Fuel Reprocessing Complex (Buildings CPP-601, CPP-603, CPP-627, CPP-640...
Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution...
Declassified 24 Sep 1973. Two detailed, conceptual process, equipment, and plant designs were prepar...
Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho Nati...
In Campaign 8, two batches of irradiated fuel from the Fast Flux Test Facility (FFTF) were processed...
Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material proper...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot pl...
After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations ...
As part of a continuing program on the development of fluid-bed fluoride volatility processes, metho...
8 2 5 6 7 6 1 1 B 3 7 3 7 reprocessing scheme which may be applicable to most power reactor fuels is...
A preliminary chemical flowsheet is presented of a fluoride volatility process for recovering and de...
The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 k...
The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 k...
For nearly four decades, the Fuel Reprocessing Complex (Buildings CPP-601, CPP-603, CPP-627, CPP-640...
Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution...
Declassified 24 Sep 1973. Two detailed, conceptual process, equipment, and plant designs were prepar...
Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho Nati...
In Campaign 8, two batches of irradiated fuel from the Fast Flux Test Facility (FFTF) were processed...
Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material proper...
Irradiated UO/sub 2/ was processed for recycle by one version of the Salt Cycle Process. The irradia...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...