Published 1994 | Version v1
Report Restricted

Pyroprocessing oxide spent nuclear fuels for efficient disposal

  • 1. Argonne National Lab., IL (United States). Chemical Technology Div.

Description

Pyrochemical processing as a means for conditioning spent nuclear fuels for disposal offers significant advantages over the direct disposal option. The advantages include reduction in high-level waste volume; conversion of most of the high-level waste to a low-level waste in which nearly all the transuranics (TRU) have been removed; and incorporation of the TRUs into a stable, highly radioactive waste form suitable for interim storage, ultimate destruction, or repository disposal. The lithium process has been under development at Argonne National Laboratory for use in pyrochemical conditioning of spent fuel for disposal. All of the process steps have been demonstrated in small-scale (0.5-kg simulated spent fuel) experiments. Engineering-scale (20-kg simulated spent fuel) demonstration of the process is underway, and small-scale experiments have been conducted with actual spent fuel from a light water reactor (LWR). The lithium process is simple, operates at relatively low temperatures, and can achieve high decontamination factors for the TRU elements. Ordinary materials, such as carbon steel, can be used for process containment

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95009901; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
ANL--CMT/CP-84354

Conference

Title
challenges and initiatives.
Acronym
Spent nuclear fuel meeting
Dates
14-16 Dec 1994.
Place
Salt Lake City, UT (United States).

Optional Information

Contract/Grant/Project number
Contract W-31109-ENG-38
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-941207--31.