Sample Results From Routine Salt Batch 7 Samples

Technical Report · Thu Jan 14 00:00:00 EST 2016

DOI:https://doi.org/10.2172/1235435· OSTI ID:1235435

Peters, T. ^[1]

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1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the “microbatches” of Integrated Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 7B have been analyzed for ²³⁸Pu, ⁹⁰Sr, ¹³⁷Cs, cations (Inductively Coupled Plasma Emission Spectroscopy - ICPES), and anions (Ion Chromatography Anions - IC-A). The analytical results from the current microbatch samples are similar to those from previous macrobatch samples. The Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU) continue to show more than adequate Pu and Sr removal, and there is a distinct positive trend in Cs removal (increasing cesium decontamination), due to the use of the Next Generation Solvent (NGS). The bulk chemistry of the DSSHT and SEHT samples do not show any signs of unusual behavior.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC09-08SR22470
• OSTI ID: 1235435
• Report Number(s): SRNL-STI-2015-00674; TRN: US1600247
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
CESIUM 137
PLUTONIUM 238
STRONTIUM 90
SOLVENT EXTRACTION
RADIOACTIVE WASTES
LIQUID WASTES
SAVANNAH RIVER PLANT
ACTINIDES
REMOVAL
DECONTAMINATION
CHEMICAL REACTIONS
SOLVENTS
QUANTITATIVE CHEMICAL ANALYSIS