Published December 2017 | Version v1
Journal article

A new, portable solvent extraction-based molybdenum-99/technetium-99m generator utilizing (n, γ) molybdenum-99 in sodium chloride solution for hospital radiopharmacy

  • 1. RPL, Regional Centre, Board of Radiation and Isotope Technology, Variable Energy Cyclotron Centre, Kolkata (India)
  • 2. Radiation Medicine Centre, Bhabha Atomic Research Centre, Mumbai (India)

Description

Technetium-99m (99mTc, t1/2= 6.02 h; 140.51 keV (89%)) is the most important and useful radioisotope in diagnostic nuclear medicine. The methyl ethyl ketone (MEK)-based solvent extraction technique is a well-known method for the separation of 99mTc from low specific activity molybdenum-99 (99Mo). Here, we report a new, portable solvent extraction-based 99Mo/99mTc generator in tandem with alumina column utilizing (n,γ) 99Mo to produce highly purified, concentrated, clinical grade 99mTc. The pH of the aqueous solution of (n,γ) 99Mo (200-500 mCi) in dilute NaOH was adjusted to 7 and saturated with solid NaCl and then transferred to an extraction tube (50 ml) kept in the lead shielded arrangement. The pertechnetate (99mTcO4−) was selectively extracted in MEK and passed through two small alumina column (neutral alumina and acidic alumina). Finally, highly pure 99mTc was recovered from acidic alumina column with 3-5 ml saline in high concentration. The performance of this new 99Mo/99mTc generator was evaluated by studying the recovery yield of 99mTc, physicochemical tests, and radiolabeling with Tc cold kits such as methylene diphosphonate (MDP), diethylene-triamine-pentaacetate acid (DTPA) and sestamibi (MIBI). The average yield of separation of 99mTc was above 90% and 99Mo breakthrough in 99mTc pertechnetate was <0.0002% (n = 10). The final 99mTcO4- fraction has the Mo and Al content <10 ppm and MEK content <0.1% v/v, with radiochemical (RC) purity >99% and radionuclidic (RN) purity >99.9%. The efficacy of labeling specific compounds was assessed using standard radiopharmaceutical kits, such as 99mTc-MDP, 99mTc-DTPA, and 99mTc-MIBI, and RC purity was above 95% (n = 6). The newly developed portable 99Mo/99mTc generator can provide the highly concentrated and purified 99mTc-pertechnetate using low specific activity 99Mo and finds its application for hospital radiopharmacy. (author)

Additional details

Publishing Information

Journal Title
Indian Journal of Nuclear Medicine
Journal Volume
32
Journal Issue
suppl
Journal Page Range
p. 17
ISSN
0972-3919

Conference

Title
49. annual conference of the society of nuclear medicine, India
Acronym
SNMI-2017
Dates
14-17 Dec 2017
Place
New Delhi (India)