Published October 2013 | Version v1
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Preliminary test for Mo recycling system in 99Mo manufacturing process (1). Reusability evaluation of Mo absorbent (Joint research)

  • 1. Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)
  • 2. ART KAGAKU Co., Ltd., Tokai, Ibaraki (Japan)
  • 3. TAIYO KOKO Co., Ltd., Kobe, Hyogo (Japan)
  • 4. Institute of Nuclear Physics (INP) of the National Nuclear Center of the Republic of Kazakhstan (NNC) (Kazakhstan)

Description

Neutron Irradiation and Testing Reactor Center has developed the production of a medical isotope of 99Mo, the parent nuclide of 99mTc by the (n, γ) method using JMTR. The (n, γ) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of 99mTc is remaining as an issue. Therefore, Polyzirconium Compound (PZC) and Polytitanium Compound (PTC) have been developed as adsorbent of molybdenum. Meanwhile, it is necessary to recycle the adsorbent and Mo for the reduction of the radioactive waste of used-adsorbent and the effective use of limited resources, respectively. This report summarizes results of the synthesis of Mo adsorbents such as PZC and PTC, and the performance tests (Characteristic of Mo adsorption/elution and Characteristic of 99Mo adsorption/99mTc elution and Characteristic of Mo recycling) with un-irradiated Mo sample and irradiated Mo sample. (author)

Availability note (English)

Available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2013-025

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Imprint Pagination
50 p.
Report number
JAEA-Technology--2013-025

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Notes
11 refs., 22 figs., 28 tabs.