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Title: Nitric-glycolic flowsheet reduction/oxidation (redox) model for the defense waste processing facility (DWPF)

Abstract

Control of the REDuction/OXidation (REDOX) state of glasses containing high concentrations of transition metals, such as High Level Waste (HLW) glasses, is critical in order to eliminate processing difficulties caused by overly reduced or overly oxidized melts. Operation of a HLW melter at Fe +2/ΣFe ratios of between 0.09 and 0.33, retains radionuclides in the melt and thus the final glass. Specifically, long-lived radioactive 99Tc species are less volatile in the reduced Tc 4+ state as TcO 2 than as NaTcO 4 or Tc 2O 7, and ruthenium radionuclides in the reduced Ru 4+ state are insoluble RuO 2 in the melt which are not as volatile as NaRuO 4 where the Ru is in the +7 oxidation state. Similarly, hazardous volatile Cr 6+ occurs in oxidized melt pools as Na 2CrO 4 or Na 2Cr 2O 7, while the Cr +3 state is less volatile and remains in the melt as NaCrO 2 or precipitates as chrome rich spinels. The melter REDOX control balances the oxidants and reductants from the feed and from processing additives such as antifoam.

Authors:
 [1];  [1];  [1];  [1];  [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1373537
Report Number(s):
SRNL-STI-2017-00005
TRN: US1800532
DOE Contract Number:  
AC09-08SR22470; AC09-76SR00001; AC09-96SR18500
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; HIGH-LEVEL RADIOACTIVE WASTES; WASTE PROCESSING; OXIDATION; REDUCTION

Citation Formats

Jantzen, C. M., Williams, M. S., Edwards, T. B., Trivelpiece, C. L., and Ramsey, W. G. Nitric-glycolic flowsheet reduction/oxidation (redox) model for the defense waste processing facility (DWPF). United States: N. p., 2017. Web. doi:10.2172/1373537.
Jantzen, C. M., Williams, M. S., Edwards, T. B., Trivelpiece, C. L., & Ramsey, W. G. Nitric-glycolic flowsheet reduction/oxidation (redox) model for the defense waste processing facility (DWPF). United States. doi:10.2172/1373537.
Jantzen, C. M., Williams, M. S., Edwards, T. B., Trivelpiece, C. L., and Ramsey, W. G. Wed . "Nitric-glycolic flowsheet reduction/oxidation (redox) model for the defense waste processing facility (DWPF)". United States. doi:10.2172/1373537. https://www.osti.gov/servlets/purl/1373537.
@article{osti_1373537,
title = {Nitric-glycolic flowsheet reduction/oxidation (redox) model for the defense waste processing facility (DWPF)},
author = {Jantzen, C. M. and Williams, M. S. and Edwards, T. B. and Trivelpiece, C. L. and Ramsey, W. G.},
abstractNote = {Control of the REDuction/OXidation (REDOX) state of glasses containing high concentrations of transition metals, such as High Level Waste (HLW) glasses, is critical in order to eliminate processing difficulties caused by overly reduced or overly oxidized melts. Operation of a HLW melter at Fe+2/ΣFe ratios of between 0.09 and 0.33, retains radionuclides in the melt and thus the final glass. Specifically, long-lived radioactive 99Tc species are less volatile in the reduced Tc4+ state as TcO2 than as NaTcO4 or Tc2O7, and ruthenium radionuclides in the reduced Ru4+ state are insoluble RuO2 in the melt which are not as volatile as NaRuO4 where the Ru is in the +7 oxidation state. Similarly, hazardous volatile Cr6+ occurs in oxidized melt pools as Na2CrO4 or Na2Cr2O7, while the Cr+3 state is less volatile and remains in the melt as NaCrO2 or precipitates as chrome rich spinels. The melter REDOX control balances the oxidants and reductants from the feed and from processing additives such as antifoam.},
doi = {10.2172/1373537},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jun 14 00:00:00 EDT 2017},
month = {Wed Jun 14 00:00:00 EDT 2017}
}

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