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Extended ion exchange process for removal and recovery of technetium from soluble waste

Technical Report ·
OSTI ID:7255644
;

A well-established method of separation of /sup 99/Tc from soluble waste is sorption of pertechnetate ion, TcO/sub 4//sup -/, onto a strong base anion exchange resin such as Dowex 1x8. Pertechnetate ion can then be removed from the resin by elution with 4M HNO/sub 3/. An improved ion exchange method which encompasses removal and recovery of /sup 99/Tc from defense waste supernate has been demonstrated. The introduction of a second ion exchange step using a weak base resin allows for the reclamation and recycling of large volumes of nitric acid generated in the initial collection of TcO/sub 4//sup -/ on the strong base resin. Also, the total amount of waste NaNO/sub 3/ which is added to the system in the process of removing /sup 99/Tc from the supernate is significantly reduced from 8% to 1%. /sup 99/Tc can be recovered from solution by precipitation as Tc/sub 2/S/sub 7/ with sulfide or as TcO/sub 2/ following reduction with aluminum or zinc amalgam, affording the ultimate recovery of the pure metal.

Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
DOE Contract Number:
AC09-76SR00001
OSTI ID:
7255644
Report Number(s):
DPST-84-507; ON: DE87002662
Country of Publication:
United States
Language:
English

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Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
HOURS LIVING RADIOISOTOPES
INTERMEDIATE MASS NUCLEI
ION EXCHANGE
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MANAGEMENT
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
PERTECHNETATES
PROCESSING
RADIOACTIVE WASTE PROCESSING
RADIOISOTOPES
REFRACTORY METAL COMPOUNDS
REMOVAL
TECHNETIUM 99
TECHNETIUM COMPOUNDS
TECHNETIUM ISOTOPES
TRANSITION ELEMENT COMPOUNDS
WASTE MANAGEMENT
WASTE PROCESSING
YEARS LIVING RADIOISOTOPES