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Title: Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

Abstract

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated inmore » future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.« less

Authors:
;
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org.:
USDOE (United States)
OSTI Identifier:
1090762
Report Number(s):
SRNL-STI2013-00437
TRN: US1400067
DOE Contract Number:  
DE-AC09-08SR22470
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; MCU, ARP, ISDP

Citation Formats

Peters, T. B., and Washington, A. L. II. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples. United States: N. p., 2013. Web. doi:10.2172/1090762.
Peters, T. B., & Washington, A. L. II. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples. United States. https://doi.org/10.2172/1090762
Peters, T. B., and Washington, A. L. II. 2013. "Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples". United States. https://doi.org/10.2172/1090762. https://www.osti.gov/servlets/purl/1090762.
@article{osti_1090762,
title = {Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples},
author = {Peters, T. B. and Washington, A. L. II},
abstractNote = {Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.},
doi = {10.2172/1090762},
url = {https://www.osti.gov/biblio/1090762}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Aug 08 00:00:00 EDT 2013},
month = {Thu Aug 08 00:00:00 EDT 2013}
}