Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 2224 Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cesium-137 sulfate and sodium) were exceeded in all three of the flowsheet tests that were performed
Laboratory experimentation has indicated that the SREX process is effective for partitioning 90 Sr f...
A Small-Column Ion-Exchange (SCIX) system is being evaluated for removing cesium from the Type 2 and...
The High Flux Isotope Reactor (HFIR) has been in operation at Oak Ridge National Laboratory since 19...
The National Spent Nuclear Fuel Program is tasked with ensuring the U.S. Department of Energy (DOE)-...
The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (...
This report examines two important generic photovoltaic technologies at particularly revealing stage...
Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that unde...
Fractional crystallization is being considered as a pretreatment method to support supplemental trea...
The Saltstone Disposal Facility (SDF), located in the Z-Area of the Savannah River Site (SRS), is us...
An innovative creep/fatigue test was run to simulate the temperature, mechanical load, and sodium co...
This report presents the work that followed the CSSX model development completed in FY2002. The deve...
A small-column ion exchange (SCIX) system has been proposed for removing cesium from the supernate a...
The transfer of liquid salt solution from Tank 26 to an evaporator is to be accomplished by activati...
Tanks for bulk liquid containment will be required to support advanced planetary exploration program...
Thin film solid regenerable adsorbent for use with sorber plate to determine gase
Laboratory experimentation has indicated that the SREX process is effective for partitioning 90 Sr f...
A Small-Column Ion-Exchange (SCIX) system is being evaluated for removing cesium from the Type 2 and...
The High Flux Isotope Reactor (HFIR) has been in operation at Oak Ridge National Laboratory since 19...
The National Spent Nuclear Fuel Program is tasked with ensuring the U.S. Department of Energy (DOE)-...
The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (...
This report examines two important generic photovoltaic technologies at particularly revealing stage...
Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that unde...
Fractional crystallization is being considered as a pretreatment method to support supplemental trea...
The Saltstone Disposal Facility (SDF), located in the Z-Area of the Savannah River Site (SRS), is us...
An innovative creep/fatigue test was run to simulate the temperature, mechanical load, and sodium co...
This report presents the work that followed the CSSX model development completed in FY2002. The deve...
A small-column ion exchange (SCIX) system has been proposed for removing cesium from the supernate a...
The transfer of liquid salt solution from Tank 26 to an evaporator is to be accomplished by activati...
Tanks for bulk liquid containment will be required to support advanced planetary exploration program...
Thin film solid regenerable adsorbent for use with sorber plate to determine gase
Laboratory experimentation has indicated that the SREX process is effective for partitioning 90 Sr f...
A Small-Column Ion-Exchange (SCIX) system is being evaluated for removing cesium from the Type 2 and...
The High Flux Isotope Reactor (HFIR) has been in operation at Oak Ridge National Laboratory since 19...