Published 2003 | Version v1
Miscellaneous

Recovery of uranium in LiF-BeF2 molten salt system by electrowinning

  • 1. KAERI, Taejon (Korea, Republic of)

Description

Fissionable uranium will be separated from long-lived nuclear materials in pyroprocess for transmutation. This study was measured decomposition voltage and deposition rate on cathode of uranium in LiF-BeF2-UF4 molten salt by electrowinning. The result of experimental is that decomposition voltage of UF4 and LiF-BeF2 molten salt is -1.4 and -1.5 volt at 500 .deg. C. Deposition rate of uranium on cathode increases with increase of uranium concentration in molten salt

Part of:
Proceedings of the Korean Radioactive Waste Society Fall, 2003

Additional details

Publishing Information

Publisher
KRWS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Radioactive Waste Society Fall, 2003
Imprint Pagination
724 p.
Journal Page Range
p. 426-430

Conference

Title
2003 Fall Meeting of the Korean Radioactive Waste Society
Dates
27-29 Nov 2003
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36017107
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ELECTROMETALLURGY; LITHIUM FLUORIDES; MATERIALS RECOVERY; MOLTEN SALTS; TRANSMUTATION; URANIUM
Descriptors DEC
ACTINIDES; ALKALI METAL COMPOUNDS; ELEMENTS; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; LITHIUM COMPOUNDS; LITHIUM HALIDES; MANAGEMENT; METALLURGY; METALS; PROCESSING; SALTS; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information

Notes
2 refs, 6 figs