Pyrochemical processing of DOE spent nuclear fuel
A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (>99.9%) separation of transuranics. The resultant waste forms from the pyroprocess, are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10118184
- Report Number(s):
- ANL/CMT/CP-84355; CONF-941207-23; ON: DE95005872; TRN: 95:002508
- Resource Relation:
- Conference: Spent nuclear fuel meeting: challenges and initiatives,Salt Lake City, UT (United States),14-16 Dec 1994; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
Similar Records
Conditioning of spent nuclear fuel for permanent disposal
Pyrometallurgical processes for recovery of actinide elements