Cyclotron Based Production of Technetium-99m
|Classificatie||6.07.4.60/31 (ALLERLEI - MEDISCHE TOEPASSINGEN -RADIO-ISOTOPES)|
|Opmerking||Online available, together with supplementary materials at Iaea.org|
Uit de publicatie:
CYCLOTRON BASED PRODUCTION OF TECHNETIUM-99m INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2017 1. INTRODUCTION Efforts and studies to investigate alternative production routes of molybdenum-99 (99Mo) and technetium-99m (99mTc) are ongoing all over the world. The direct production of 99mTc using accelerators is one of the proposed alternatives that utilizes the 100Mo(p,2n)99mTc reaction on highly 100Mo-enriched target material [1–5]. A Coordinated Research Project (CRP) on Accelerator-based Alternatives to Non-HEU Production of 99Mo/99mTc was initiated with the aim of developing an alternative direct method of production of 99mTc using dedicated high current cyclotrons. There are several potential methods for the production of 99mTc from accelerators. These have been explored in a recent publication by the OECD Nuclear Energy Agency in 2010 . An IAEA consultants meeting was held in 2011 to review the current status of research and development of and the perspective for the accelerator based production of 99mTc. The meeting concluded with the suggestion that the IAEA initiate a CRP on the development of accelerator based alternatives to the 99Mo/99mTc generator, with an emphasis on several outstanding issues that need further research and development, including: —— The purity of the final 99mTc product with regard to both the isotopic ratio of the molybdenum starting material and the proton energy. —— Approaches to isolating and purifying the 99mTc extracted from the target material. A more complete understanding regarding reproducibility, purity and efficiency for these approaches is needed and should use prescribed metrics for direct comparisons. —— The impact of specific activity (99mTc / all Tc isotopes including 99gTc) has to be determined in order to define the shelf life of accelerator produced 99mTc compared with generator produced 99mTc in the formulation of radiopharmaceutical kits. —— The path to recovery of the enriched 100Mo target material including the tracking of the isotopic composition and chemical and radionuclidic impurities. It was noted by the expert panel assembled that the proposed CRP on direct production may also be a long term solution and is quite sufficient to manufacture 99mTc on-site for supplying regional radiopharmacies and may supplement or in some instances even replace 99Mo generators.