• Title/Summary/Keyword: radiation safety

Search Result 1,502, Processing Time 0.022 seconds

Consideration of a Bacteria Contamination Management in the Dispensation of 99mTc Radiopharmaceutical (테크네슘 방사성의약품의 조제와 분배 과정에서 오염균에 대한 고찰)

  • Choi, Do Chul;Gim, Yeong Su;Jo, Gwang Mo;Gim, Hui Jeong;Seo, Han Gyeong
    • The Korean Journal of Nuclear Medicine Technology
    • /
    • v.22 no.2
    • /
    • pp.84-87
    • /
    • 2018
  • Purpose The radiopharmaceutical used in the nuclear medicine department is used only for the specific patient according to the prescription or instruction of the doctor without selling, so it is dispensed and it is distributed and used for the examination. Radiopharmaceuticals administered to patients should be managed appropriately as well as radiation safety management during dispensation. The purpose of this study is to investigate microbial contamination during dispensation of radiopharmaceuticals Materials and Methods This study distinguished between general workbench and clean workbench and performed three tests. First, microbial cultivation test of radiopharmaceutical prepared and dispensed in general workbenches and sterile workbenches were carried out five times, respectively. The second test was performed settle plate method three times before and after the use of the exhaust filter. Finally, Adenosine Triphosphate (ATP) measurement was performed in each workbench to measure bacterial counts. In addition, ATP measurement were carried out by designating locations and items that may be contaminated during dispensation. Results In the microbial culture test, no microorganisms were detected in both samples. In the settle plate method, it was detected without using of the exhaust filter in a general workbench once. In the ATP measurement test, it was measured at the level of 400 RLU or less, which is the standard value of contamination, in both workbenches surface. In additional ATP measurement test, the refrigerator handle in the distribution room was measured above the reference value of 1217 RLU, the vacuum vial shield of the Tech Generator at 435 RLU, and the syringe holder at 1357 RLU. After environmental disinfection, the results were reduced to 311 RLU, 136 RLU, and 291 RLU. Conclusion No contamination by bacteria was found in both workbenches. However, microbial contamination may occur if the use of an exhaust filter or proper hand hygiene is not achieved. Regular inspections and management for aseptic processing themselves will be necessary.

Operation of dry distillation process on the production of radionuclide 131I at Puspiptek area Serpong Indonesia, 2021 to 2022

  • Chaidir Pratama;Daya Agung Sarwono;Ahid Nurmanjaya;Abidin Abidin;Triyatna Fani;Moch Subechi;Endang Sarmini;Enny Lestari;Yanto Yanto;Kukuh Eka Prasetya;Maskur Maskur;Fernanto Rindiyantono;Indra Saptiama;Anung Pujiyanto;Herlan Setiawan;Tita Puspitasari;Marlina Marlina;Hasnel Sofyan;Budi Setiawan;Miftakul Munir;Heny Suseno
    • Nuclear Engineering and Technology
    • /
    • v.56 no.4
    • /
    • pp.1526-1531
    • /
    • 2024
  • 131I is a fission product produced in a nuclear reactor by irradiating tellurium dioxide, with a half-life of 8.02 day. The most important and widely used method for making 131I is irradiation using a nuclear reactor and post-irradiation followed by dry distillation. The advantage of the dry distillation process is that the process and the equipment are relatively simple, namely TeO2 (m.p. 750 ℃), which can withstand heating during reactor irradiation. Based on TeO2 irradiation by neutron following the technique of dry distillation was explained for production of 131I on a large scale. A dry distillation followed the radioisotope production operation using the 30 MW GA Siwabessy nuclear reactor to meet national demand. TeO2 targets are 25 and 50 g irradiated for 87-100 h. The resulting 131I activity is 20.29339-368.50335GBq. According to the requirements imposed on the radionuclide purity of the preparation, the contribution of 131I training in the resulting preparation was not less than 99.9 %