Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products

Separation Science and Technology

Volumn 41, Issue 10, 2006, Pages 1965-1983

  Herrmann, S D ^a   Li, S X ^a   Simpson, M F ^a   Phongikaroon, S ^a  

^a IDAHO NATIONAL LABORATORY   (United States)

Author keywords

Electrolytic reduction; Electrometallurgical treatment; Molten LiCl Li 2O; Oxide reduction; Pyrochemical processing; Spent oxide fuel treatment

Indexed keywords

ACTINIDES; ELECTROLYTIC REDUCTION; MECHANICAL PERMEABILITY; SALTS; SEPARATION; STAINLESS STEEL;

ELECTROMETALLURGICAL TREATMENT; MOLTEN LICL/LI2O; OXIDE REDUCTION; PYROCHEMICAL PROCESSING; SPENT OXIDE FUEL TREATMENT;

NUCLEAR FUELS;

ACTINIDES; ELECTROLYTIC REDUCTION; MECHANICAL PERMEABILITY; NUCLEAR FUELS; SALTS; SEPARATION; STAINLESS STEEL;

ELECTROLYSIS; FUEL; LOADING (TESTING); OXIDE; PERMEABILITY; SEPARATION; STEEL;

EID: 33746198191     PISSN: 01496395     EISSN: 15205754     Source Type: Journal    
DOI: 10.1080/01496390600745602     Document Type: Conference Paper

References (5)

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