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Title: Monosodium titanate particle characterization

Abstract

A characterization study was performed on monosodium titanate (MST) particles to determine the effect of high shear forces expected from the In-Tank Precipitation (ITP) process pumps on the particle size distribution. The particles were characterized using particle size analysis and scanning electron microscopy (SEM). No significant changes in particle size distributions were observed between as-received MST and after 2--4 hours of shearing. Both as-received and sheared MST particles contained a large percentage of porosity with pore sizes on the order of 500 to 2,000 Angstroms. Because of the large percentage of porosity, the overall surface area of the MST is dominated by the internal surfaces. The uranium and plutonium species present in the waste solution will have access to both interior and exterior surfaces. Therefore, uranium and plutonium loading should not be a strong function of MST particle size.

Authors:
;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
6509750
Report Number(s):
WSRC-TR-93-029
ON: DE93015890
DOE Contract Number:
AC09-89SR18035
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; SAVANNAH RIVER PLANT; RADIOACTIVE WASTE PROCESSING; SODIUM COMPOUNDS; PARTICLE SIZE; TITANATES; DISTRIBUTION; HIGH-LEVEL RADIOACTIVE WASTES; MECHANICAL PROPERTIES; MORPHOLOGY; PARTICLES; PLUTONIUM 239; POROSITY; PRECIPITATION; SCANNING ELECTRON MICROSCOPY; SHEAR; STRONTIUM ISOTOPES; SURFACE AREA; URANIUM 235; ACTINIDE ISO; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALKALI METAL COMPOUNDS; ALKALINE EARTH ISOTOPES; ALPHA DECAY RADIOISOTOPES; ELECTRON MICROSCOPY; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; MICROSCOPY; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; RADIOISOTOPES; SEPARATION PROCESSES; SIZE; SPONTANEOUS FISSION RADIOISOTOPES; SURFACE PROPERTIES; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; URANIUM ISOTOPES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES; 052001* - Nuclear Fuels- Waste Processing; 360603 - Materials- Properties

Citation Formats

Chandler, G.T., and Hobbs, D.T.. Monosodium titanate particle characterization. United States: N. p., 1993. Web. doi:10.2172/6509750.
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Chandler, G.T., & Hobbs, D.T.. Monosodium titanate particle characterization. United States. doi:10.2172/6509750.
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Chandler, G.T., and Hobbs, D.T.. Tue . "Monosodium titanate particle characterization". United States. doi:10.2172/6509750. https://www.osti.gov/servlets/purl/6509750.
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@article{osti_6509750,
title = {Monosodium titanate particle characterization},
author = {Chandler, G.T. and Hobbs, D.T.},
abstractNote = {A characterization study was performed on monosodium titanate (MST) particles to determine the effect of high shear forces expected from the In-Tank Precipitation (ITP) process pumps on the particle size distribution. The particles were characterized using particle size analysis and scanning electron microscopy (SEM). No significant changes in particle size distributions were observed between as-received MST and after 2--4 hours of shearing. Both as-received and sheared MST particles contained a large percentage of porosity with pore sizes on the order of 500 to 2,000 Angstroms. Because of the large percentage of porosity, the overall surface area of the MST is dominated by the internal surfaces. The uranium and plutonium species present in the waste solution will have access to both interior and exterior surfaces. Therefore, uranium and plutonium loading should not be a strong function of MST particle size.},
doi = {10.2172/6509750},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 12 00:00:00 EST 1993},
month = {Tue Jan 12 00:00:00 EST 1993}
}
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Technical Report:
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DOI:  10.2172/6509750
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  • ;
    A characterization study was performed on monosodium titanate (MST) particles to determine the effect of high shear forces expected from the In-Tank Precipitation (ITP) process pumps on the particle size distribution. The particles were characterized using particle size analysis and scanning electron microscopy (SEM). No significant changes in particle size distributions were observed between as-received MST and after 2--4 hours of shearing. Both as-received and sheared MST particles contained a large percentage of porosity with pore sizes on the order of 500 to 2,000 Angstroms. Because of the large percentage of porosity, the overall surface area of the MST ismore » dominated by the internal surfaces. The uranium and plutonium species present in the waste solution will have access to both interior and exterior surfaces. Therefore, uranium and plutonium loading should not be a strong function of MST particle size.« less

  • The authors reviewed and compiled typical data from prior measurements of the size of simulated sludge, actual sludge, and monosodium titanate (MST) particles. For the actual waste, the authors attempted to collect all available data from prior measurements. Since few prior measurements exist and since these analyses occurred using different analytical methods that span over two decades, the authors cannot verify the consistency of the methods used to make the measurements nor fully ensure the reliability of the information.

  • This report discusses the characterization of the nature of Sr{sup 2+} sorption on MST in HLW salt solutions.

  • ; ;
    Engineered forms of MST and mMST were prepared at ORNL using an internal gelation process. Samples of these two materials were characterized at SRNL to examine particle size and morphology, peroxide content, tapped densities, and Na, Ti, and C content. Batch contact tests were also performed to examine the performance of the materials. The {sup E}mMST material was found to contain less than 10% of the peroxide found in a freshly prepared batch of mMST. This was also evidenced in batch contact testing with both simulated and actual waste, where little difference in performance was seen between the two engineeredmore » materials, {sup E}MST and {sup E}mMST. Based on these results, attempts were made to increase the peroxide content of the materials by post-treatment with hydrogen peroxide. The peroxide treatment resulted in a slight ({approx}10%) increase in peroxide content; however, the peroxide:Ti molar ratio was still much lower ({approx}0.1 X) than what is seen in a freshly prepared batch of mMST. Testing with simulated waste showed the performance of the peroxide treated materials was improved. Batch contact tests were also performed with an earlier (2003) prepared lot of {sup E}MST to examine the effect of ionic strength on the performance of the material. In general the results showed a decrease in removal performance with increasing ionic strength, which is consistent with previous testing with MST. A Sr loading isotherm was also determined, and the {sup E}MST material was found to reach a Sr loading as high as 13.2 wt % after 100 days of contact at a phase ratio of 20000 mL/g. At the typical MST phase ratio of 2500 mL/g (0.4 g/L), a Sr loading of 2.64 wt % was reached after 506 hours of contact. Samples of {sup E}MST and the post-peroxide treated {sup E}mMST were also tested in a column configuration using simulated waste solution. The breakthrough curves along with analysis of the sorbent beds at the conclusion of the experiments showed that the peroxide treated {sup E}mMST has a higher Sr and Np capacity, but that both materials have similar Pu capacities. The {sup E}MST removed a larger percentage of U than the peroxide treated {sup E}mMST, which is consistent with previous testing which showed that mMST has little affinity for U under these conditions.« less

  • ;
    The solubilities of plutonium and uranium have been determined for alkaline salt solutions having compositions which bound those which will be processed in the In-Tank Precipitation (ITP) process. Loadings of plutonium and uranium onto monosodium titanate (MST) have been determined at temperatures bounding those expected to occur during ITP and using a salt solution which was determined to have the maximum solubility for uranium and plutonium. Fissile loadings increase with decreasing amounts of MST in contact with the salt solutions saturated in plutonium and uranium. At MST concentrations bounding those which are planned for the ITP process, expressions for themore » maximum loadings (wt %) are determined to be 0.29 - 0.20x[MST] for plutonium and 1.8 - 0.29x[MST] for uranium, where [MST] is the concentration of MST in grams/liter. These expressions are valid over the range of MST concentrations from 0.05 to 0.51 g/L and temperatures of 17[degrees]--74[degrees]C. These loadings are below the individual infinitely safe limits for plutonium and uranium. Additional confirmatory experiments are planned to verify the effects of temperature and multiple contacts of the MST with fresh salt solution on the fissile loadings.« less