Characterization of Supernate Samples from HLW Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H
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). Results and observations obtained from testing include the following. All tanks will require cesium removal as well as treatment with Monosodium Titanate (MST) for 90Sr (Strontium) decontamination. A small filtration effect for 90Sr was observed for five of the seven tank wastes. No filtration effects were observed for Pu (Plutonium), Np (Neptunium), U (Uranium), or Tc (Technetium). 137Cs (Cesium) concentration is approximately E+09 pCi/mL for all the tank wastes. Tank 37H is significantly higher in 90Sr than the other six tanks. 237Np in the F-Area tanks(45F and 46F) are at least 1 order of magnitude less than the H-Area tank wastes. The data indicate a constant ratio of 99Tc to Cs in the seven tank wastes. This indicates the Tc remains largely soluble in Savannah River Site (SRS) waste and partition similarly with Cs. 241Am (Americium) concentration was low in the seven tank wastes. The majority of data were detection limit values, the largest being less than 1.0E+04 pCi/mL. Measured values for Pu and U were generally well below solubility model predictions.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 835577
- Report Number(s):
- WSRC-TR-2004-00386; TRN: US0500082
- Resource Relation:
- Other Information: PBD: 2 Jul 2004
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AMERICIUM
CESIUM
DECONTAMINATION
FILTRATION
MOLYBDOPHOSPHATES
NEPTUNIUM
PLUTONIUM
PROCESSING
REMOVAL
SODIUM
SOLUBILITY
STRONTIUM
TANKS
TECHNETIUM
TESTING
TITANATES
URANIUM
VERIFICATION
WASTE PROCESSING
SUPERNATE
SAMPLES
CHARACTERIZATION