Published January 17, 1995 | Version v1
Patent Metadata-only

Decontamination method for technetium in spent fuel reprocessing co-decontamination step

Creators

Description

An aqueous solution of Tc back-extraction from a Tc back-extraction step disposed after U-Pu extraction and cleaning steps (main extraction step) in a co-decontamination step of a spent nuclear fuel reprocessing step is joined as it is to a preceding extraction (cleaning) step. With such procedure, U and Pu contained in the aqueous solution of the Tc back-extraction step are recovered in the extraction step of the main extraction step, and Tc is discharged to a high level aqueous phase liquid wastes. Accordingly, since an auxiliary extraction step for separating U and Pu from Tc is no more necessary, the processing step can be extremely simplified in view of the process. (T.M.)

Availability note (English)

Available from JAPIO. Also available from EPO.

Additional details

Publishing Information

Imprint Pagination
5 p.
IPC:
Int. Cl. G21C19/46; G21F9/06.
IPC
Int. Cl. G21C19/46; G21F9/06.
Patent number
JP patent document 7-12986/A/

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
26065626
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
DECONTAMINATION; PLUTONIUM; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE PROCESSING; REPROCESSING; SEPARATION PROCESSES; SOLVENT EXTRACTION; SPENT FUELS; TECHNETIUM; URANIUM
Descriptors DEC
ACTINIDES; CLEANING; ELEMENTS; ENERGY SOURCES; EXTRACTION; FUELS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information

Secondary number(s)
JP patent application 5-149335.