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Title: Recycle of enriched Mo targets for economic production of 99Mo/99mTc medical isotope without use of enriched uranium

Journal Article · · Journal of Radioanalytical and Nuclear Chemistry
 [1];  [1]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)

A new recycle process for recovery of enriched 98Mo or 100Mo used for production of 99Mo/99mTc medical isotope was developed. In this process, Mo is precipitated from spent NorthStar Mo/Tc generator solution containing ~200 g/L Mo as K2MoO4 in 5 M KOH using acetic acid and then washed with nitric acid. High purification factors from potassium were achieved, and typical Mo recovery yields were ~95 %. In conclusion, the recycle process was performed with up to 260 g of Mo per batch and can be easily implemented for processing of up to 400 g of Mo.

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1399098
Journal Information:
Journal of Radioanalytical and Nuclear Chemistry, Vol. 308, Issue 1; ISSN 0236-5731
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 14 works
Citation information provided by
Web of Science

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Cited By (2)

99mTc production via the (γ, n) reaction on natural Mo journal August 2018
Electron-tracking Compton camera imaging of technetium-95m journal December 2018