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Title: TANK 21H SUPERNATE SAMPLE CROSS-CHECK ANALYSIS - 2007

Abstract

The intent of this analysis was to perform cross-checks against routine F/H Lab analyses (corrosion, enrichment, soluble uranium, plutonium and feed qualification program). This Tank 21H supernate sample was analyzed mainly for the following contaminants and radionuclides: free OH{sup -}, NO{sub 2}{sup -}, NO{sub 3}{sup -}, SO{sub 4}{sup -2}, CO{sub 3}{sup -2}, Al, Si, Na and Pu-isotopes, total gamma and U- isotopes.

Authors:
;
Publication Date:
Research Org.:
SRS
Sponsoring Org.:
USDOE
OSTI Identifier:
914552
Report Number(s):
WSRC-TR-2007-00149
TRN: US0803317
DOE Contract Number:
DE-AC09-96SR18500
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTES; LIQUID WASTES; CHEMICAL ANALYSIS; PLUTONIUM ISOTOPES; URANIUM ISOTOPES; STORAGE FACILITIES; HYDROXIDES; NITRITES; NITRATES; SULFATES; CARBONYLS; ALUMINIUM; SILICON; SODIUM

Citation Formats

Oji, L, and Shirley Mccollum, S. TANK 21H SUPERNATE SAMPLE CROSS-CHECK ANALYSIS - 2007. United States: N. p., 2007. Web. doi:10.2172/914552.
Oji, L, & Shirley Mccollum, S. TANK 21H SUPERNATE SAMPLE CROSS-CHECK ANALYSIS - 2007. United States. doi:10.2172/914552.
Oji, L, and Shirley Mccollum, S. Wed . "TANK 21H SUPERNATE SAMPLE CROSS-CHECK ANALYSIS - 2007". United States. doi:10.2172/914552. https://www.osti.gov/servlets/purl/914552.
@article{osti_914552,
title = {TANK 21H SUPERNATE SAMPLE CROSS-CHECK ANALYSIS - 2007},
author = {Oji, L and Shirley Mccollum, S},
abstractNote = {The intent of this analysis was to perform cross-checks against routine F/H Lab analyses (corrosion, enrichment, soluble uranium, plutonium and feed qualification program). This Tank 21H supernate sample was analyzed mainly for the following contaminants and radionuclides: free OH{sup -}, NO{sub 2}{sup -}, NO{sub 3}{sup -}, SO{sub 4}{sup -2}, CO{sub 3}{sup -2}, Al, Si, Na and Pu-isotopes, total gamma and U- isotopes.},
doi = {10.2172/914552},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 04 00:00:00 EDT 2007},
month = {Wed Apr 04 00:00:00 EDT 2007}
}

Technical Report:

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  • This report summarizes the analytical data reported by the F/H and Savannah River National Laboratories for the 2012 cross-check analysis for high level waste supernatant liquid samples from SRS Tanks 30 and 37. The intent of this Tank 30 and 37 sample analyses was to perform cross-checks against routine F/H Laboratory analyses (corrosion and evaporator feed qualification programs) using samples collected at the same time from both tanks as well as split samples from the tanks.
  • This report provides the final results of analyses of the saltcake core sample and a separate supernate sample from Tank 29H. The supernate sample was markedly different from the drained interstitial liquid. The Tank 29H supernate had a reduction in 238Pu upon filtering through a 0.45-micron filter. Approximately 25 per cent of the U is in suspension in the supernate and can be removed by filtration. As expected, the radionuclides Cs-137 and Tc-99 are entirely soluble and the actinides are largely insoluble, in the interstitial liquid, within experimental error. It is not known how representative this saltcake sample is formore » the entire tank. There is considerably more liquid present in this sample than in most other tank samples examined thus far. The history of the tank indicates that some of the saltcake in the top layer likely dissolved by the addition of low ionic strength solutions over the past few years. Also, the sample was collected at the bottom of a 7-foot well that was mined into the saltcake with water. These water additions could have dissolved the sodium nitrate in the top layer, and left behind a layer containing the remaining salts, including those of aluminum, although it is not possible to confirm this with this sample. Conversely, if this high aluminum composition is similar throughout the tank, more interstitial liquid may be released upon draining, and more will be retained by the remaining saltcake. The draining characteristics of a high aluminum composition waste are also expected to be different from those of sodium nitrate, although the impact is not known. The high concentration of aluminum species led to precipitation of aluminum hydroxide during a draining/dissolution test using deionized water. If this occurs during tank retrieval, it has significant impacts for tank waste retrieval schedules. This phenomenon would likely manifest as slow dissolution and percolation rates, depending on the volume of the high aluminum region, and the method of water addition.« less
  • This report provides details of the characterization of Tank 38H saltcake and supernate samples pulled in September 2003. The core sample HTF-E-03-114 contained approximately 4 inches of saltcake, which was soupy and brown with white chunks, and contained less than 15 mL of cloudy free liquid. The undrained bulk saltcake had a water content of 16.8 percentage weight and a bulk density that was approximately 1.94 g/cm3 at full saturation. The 137Cs activity of the bulk saltcake in sample HTF-E-03-114 was 3.72E+7 pCi/g, which corresponds to 0.3 Ci per gallon of saltcake. The 238Pu activity of the bulk saltcake wasmore » 3.62E+6 pCi/g. The filtered free liquid in sample HTF-E-03-114 had a density of 1.430 g/cm3, a 137Cs activity of 0.73 Ci/gal., and a 238Pu activity of 5.78E+3 pCi/mL. The solids filtered from the HTF-E-03-114 free liquid were primarily composed of salts (sodium nitrate and sodium carbonate monohydrate) and sodium aluminosilicates. The Tank 38H supernate samples (HTF-E-03-122 and 123) had a density of 1.45 g/cm3, a 137Cs activity of 0.65 Ci/gal, a 238Pu activity of 2.2E4 pCi/mL, and contained no visible insoluble solids. The viscosity of supernate samples HTF-E-03-122 and 123 was determined at 25 degrees Celsius, 35 degrees Celsius, and 50 degrees Celsius to be 12.1 cP, 8.1 cP, and 5.1 cP, respectively. An exponential correlation for the Tank 38H supernate viscosity was formulated for use over this temperature range. In the undrained saltcake sample, several components, including cesium, nitrite, hydroxide, phosphate, formate, and potassium, were partitioned predominantly into the interstitial liquid. Although the plutonium, uranium, neptunium, and strontium activities in the Tank 38H saltcake core sample are high compared with recent Tank 41H samples, they are low compared with previous saltcake samples from Tank 38H collected in July 2000 and July 2001. The 137Cs of the Tank 38H saltcake sample is comparable with the previous Tank 38H saltcake samples.« less
  • Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.
  • Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tankmore » Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.« less