Countercurrent flowsheet testing of the TRUEX process with ICPP calcine

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Description

Calcine was generated at the Idaho Chemical Processing Plant over several decades as a method of solidifying numerous raffinates and wastes from spent nuclear fuel reprocessing for convenient interim storage. Unfortunately, the bulk of the calcine is inert, with radionuclides comprising less than 1 weight percent of the total calcine mass. The bulk of the calcine currently stored at the ICPP was produced from wastes generated during reprocessing of zirconium clad fuels. Consequently, this material contains varying, but large quantities of zirconium oxide. Currently, separations options are being considered for acidic solutions of dissolved ICPP calcines to minimize high level ... continued below

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5 p.

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Law, J.D.; Herbst, R.S.; Brewer, K.N. & Todd, T.A. July 1, 1998.

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Description

Calcine was generated at the Idaho Chemical Processing Plant over several decades as a method of solidifying numerous raffinates and wastes from spent nuclear fuel reprocessing for convenient interim storage. Unfortunately, the bulk of the calcine is inert, with radionuclides comprising less than 1 weight percent of the total calcine mass. The bulk of the calcine currently stored at the ICPP was produced from wastes generated during reprocessing of zirconium clad fuels. Consequently, this material contains varying, but large quantities of zirconium oxide. Currently, separations options are being considered for acidic solutions of dissolved ICPP calcines to minimize high level waste volumes and economic penalties perceived for final disposal of these wastes. The actinide separation process being emphasized for the dissolved calcine solutions is the TRUEX process. Substantial problems have been encountered during TRUEX flowsheet development efforts for dissolved zirconium calcine simulant due to the high concentrations and subsequent extraction of zirconium from the feed. Alteration of the calcine dissolution parameters has resulted in the development of a successful TRUEX/Zr calcine baseline flowsheet. This flowsheet has been tested using 22 stages of a 2.0 centimeter diameter centrifugal contactor pilot plant using simulated dissolved Zr calcine solution. With this flowsheet, a removal efficiency of > 96% was obtained for {sup 241}Am (analytical detection limits were reached). Less than 0.25% of the {sup 95}Zr exited with the high-level waste strip product.

Physical Description

5 p.

Notes

INIS; OSTI as DE98056073

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  • SPECTRUM `98: nuclear and hazardous waste management international topical meeting, Denver, CO (United States), 13-18 Sep 1998

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  • Other: DE98056073
  • Report No.: INEEL/CON--97-01432
  • Report No.: CONF-980905--
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/656585 | External Link
  • Office of Scientific & Technical Information Report Number: 656585
  • Archival Resource Key: ark:/67531/metadc705825

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

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Creation Date

  • July 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • July 19, 2016, 12:07 p.m.

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Law, J.D.; Herbst, R.S.; Brewer, K.N. & Todd, T.A. Countercurrent flowsheet testing of the TRUEX process with ICPP calcine, report, July 1, 1998; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc705825/: accessed January 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.