A possible disposition pathway for the residue from the abandoned In-Tank Precipitation (ITP) sends the material from Tank 48H in increments to Saltstone via aggregation in Tank 50H. After entering Tank 50H, the amount of fissile material sorbed on MST may increase as a result of contacting waste solutions with dissolved uranium and plutonium. SRNL recommends that nuclear criticality safety evaluations use uranium and plutonium loadings onto MST of 14.0 {+-} 1.04 weight percent (wt %) for uranium and 2.79 {+-} 0.197 wt % for plutonium given the assumed streams defined in this report. These values derive from recently measured for conditions relevant to the Actinide Removal Process (ARP) and serve as conservative upper bounds for uranium and...
The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and...
Monosodium titanate (MST) is an inorganic adsorbent powder that effectively removes strontium, pluto...
This Criticality Safety Evaluation Report analyzes the stabilization of plutonium/uranium solutions ...
This report describes the results of an experimental study to measure the sorption of fissile actini...
This report focuses solely on the accumulation of uranium and plutonium during In-Tank Precipitation...
The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and...
Testing examined the extent and rate of strontium, plutonium, uranium, and neptunium removal from ra...
Research over the past decade has studied the adsorption of plutonium and uranium onto monosodium ti...
The DA isotherm parameters for U, Pu, Sr and Np have been updated to include additional data obtaine...
Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in...
The current design of the Salt Waste Processing Facility (SWPF) includes an auxiliary facility, the ...
As part of preparations to use the Tank 50H as a receiving tank for the salt supernate solution desi...
High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS)...
The DOE Office of Waste Processing recently funded supplemental Phase II testing to further investig...
The Salt Disposition Systems Engineering Team identified the adsorption kinetics of actinides and st...
The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and...
Monosodium titanate (MST) is an inorganic adsorbent powder that effectively removes strontium, pluto...
This Criticality Safety Evaluation Report analyzes the stabilization of plutonium/uranium solutions ...
This report describes the results of an experimental study to measure the sorption of fissile actini...
This report focuses solely on the accumulation of uranium and plutonium during In-Tank Precipitation...
The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and...
Testing examined the extent and rate of strontium, plutonium, uranium, and neptunium removal from ra...
Research over the past decade has studied the adsorption of plutonium and uranium onto monosodium ti...
The DA isotherm parameters for U, Pu, Sr and Np have been updated to include additional data obtaine...
Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in...
The current design of the Salt Waste Processing Facility (SWPF) includes an auxiliary facility, the ...
As part of preparations to use the Tank 50H as a receiving tank for the salt supernate solution desi...
High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS)...
The DOE Office of Waste Processing recently funded supplemental Phase II testing to further investig...
The Salt Disposition Systems Engineering Team identified the adsorption kinetics of actinides and st...
The study of the effects of contacting a simulated salt solution spiked with uranium, plutonium, and...
Monosodium titanate (MST) is an inorganic adsorbent powder that effectively removes strontium, pluto...
This Criticality Safety Evaluation Report analyzes the stabilization of plutonium/uranium solutions ...