Pyrochemical separation of radioactive components from inert materials in ICPP high-level calcined waste

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Description

Since 1963, calcination of aqueous wastes from reprocessing of DOE-owned spent nuclear fuels has resulted in the accumulation of approximately 3800 m{sup 3} of high-level waste (HLW) at the Idaho Chemical Processing Plant (ICPP). The waste is in the form of a granular solid called calcine and is stored on site in stainless steel bins which are encased in concrete. Due to the leachability of {sup 137}Cs and {sup 90}Sr and possibly other radioactive components, the calcine is not suitable for final disposal. Hence, a process to immobilize calcine in glass is being developed. Since radioactive components represent less than ... continued below

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11 p.

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Del Debbio, J.A.; Nelson, L.O. & Todd, T.A. May 1, 1995.

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Description

Since 1963, calcination of aqueous wastes from reprocessing of DOE-owned spent nuclear fuels has resulted in the accumulation of approximately 3800 m{sup 3} of high-level waste (HLW) at the Idaho Chemical Processing Plant (ICPP). The waste is in the form of a granular solid called calcine and is stored on site in stainless steel bins which are encased in concrete. Due to the leachability of {sup 137}Cs and {sup 90}Sr and possibly other radioactive components, the calcine is not suitable for final disposal. Hence, a process to immobilize calcine in glass is being developed. Since radioactive components represent less than 1 wt % of the calcine, separation of actinides and fission products from inert components is being considered to reduce the volume of HLW requiring final disposal. Current estimates indicate that compared to direct vitrification, a volume reduction factor of 10 could result in significant cost savings. Aqueous processes, which involve calcine dissolution in nitric acid followed by separation of actinide and fission products by solvent extraction and ion exchange methods, are being developed. Pyrochemical separation methods, which generate small volumes of aqueous wastes and do not require calcine dissolution, have been evaluated as alternatives to aqueous processes. This report describes three proposed pyrochemical flowsheets and presents the results of experimental studies conducted to evaluate their feasibility. The information presented is a consolidation of three reports, which should be consulted for experimental details.

Physical Description

11 p.

Notes

INIS; OSTI as DE96001559

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  • Other Information: PBD: May 1995

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  • Other: DE96001559
  • Report No.: INEL--95/0154
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/152020 | External Link
  • Office of Scientific & Technical Information Report Number: 152020
  • Archival Resource Key: ark:/67531/metadc622094

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • May 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • Feb. 24, 2016, 6:50 p.m.

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Del Debbio, J.A.; Nelson, L.O. & Todd, T.A. Pyrochemical separation of radioactive components from inert materials in ICPP high-level calcined waste, report, May 1, 1995; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc622094/: accessed December 14, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.