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Characterization of Supernate Samples from High Level Waste Tanks 13H, 30H, 37H, 39H, 45F, 46F and 49H.

DE2005835577

Publication Date	2004
Personal Author	Stallings, M. E.; Barnes, M. J.; Peters, T. B.; Fondeur, F. F.; Hobbs, D. T.; Fink, S. D.
Page Count	84
Abstract	This document presents work conducted in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractor for the Salt Waste Processing Facility (SWPF). The Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) analyze and characterize supernate waste from seven selected High Level Waste (HLW) tanks to allow classification of feed to be sent to the SWPF, verification that SWPF processes will be able to meet Saltstone Waste Acceptance Criteria (WAC), and updating of the Waste Characterization System (WCS) database. This document provides characterization data of samples obtained from Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H and discusses results. Characterization of the waste tank samples involved several treatments and analysis at various stages of sample processing. These analytical stages included as-received liquid, post-dilution to 6.44 M sodium (target), post-acid digestion, post-filtration (at 3 filtration pore sizes), and after cesium removal using ammonium molybdophosphate (AMP).
Keywords	High level radioactive wastes Tanks Americium Cesium Decontamination Filtration Molybdophosphates Neptunium Plutonium Radioactive waste processing Removal Sodium Solubility Strontium Technetium Testing Titanates Uranium Verification
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Westinghouse Savannah River Co., Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200518

Characterization of Supernate Samples from High Level Waste Tanks 13H, 30H, 37H, 39H, 45F, 46F and 49H.

Characterization of Supernate Samples from High Level Waste Tanks 13H, 30H, 37H, 39H, 45F, 46F and 49H.
DE2005835577

Publication Date	2004
Personal Author	Stallings, M. E.; Barnes, M. J.; Peters, T. B.; Fondeur, F. F.; Hobbs, D. T.; Fink, S. D.
Page Count	84
Abstract	This document presents work conducted in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractor for the Salt Waste Processing Facility (SWPF). The Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) analyze and characterize supernate waste from seven selected High Level Waste (HLW) tanks to allow classification of feed to be sent to the SWPF, verification that SWPF processes will be able to meet Saltstone Waste Acceptance Criteria (WAC), and updating of the Waste Characterization System (WCS) database. This document provides characterization data of samples obtained from Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H and discusses results. Characterization of the waste tank samples involved several treatments and analysis at various stages of sample processing. These analytical stages included as-received liquid, post-dilution to 6.44 M sodium (target), post-acid digestion, post-filtration (at 3 filtration pore sizes), and after cesium removal using ammonium molybdophosphate (AMP).
Keywords	High level radioactive wastes Tanks Americium Cesium Decontamination Filtration Molybdophosphates Neptunium Plutonium Radioactive waste processing Removal Sodium Solubility Strontium Technetium Testing Titanates Uranium Verification
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Westinghouse Savannah River Co., Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200518