Results of Analyses of Tank 37H Criticality Salt Samples (HTK-493 and 494)
High Level Waste Division (HLWD) personnel requested Savannah River Technology Center (SRTC) support in analyzing samples of salt cake from Tank 37H as input to a Nuclear Criticality Safety Evaluation (NCSE) in support of dissolution of the salt in the tank. Two salt core samples (HTK-493 and 494) were pulled from Tank 37H and transferred to the SRTC Shielded Cells Facility on April 2, 2002 for analyses of species that may affect criticality as the salt is dissolved. The core samples were composited and prepared for analysis of the as-received sample and of insoluble solids separated from as-received sample. Results of the analyses are presented herein. Results are given for the as-received salt cake, for insoluble solids separated from the core sample both with and without a correction for soluble solids remaining after dissolution, and for wash water produced by dissolving the soluble salts in inhibited water.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 799424
- Report Number(s):
- WSRC-TR-2002-00244; TRN: US0300035
- Resource Relation:
- Other Information: PBD: 10 Jul 2002
- Country of Publication:
- United States
- Language:
- English
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