Dosimetry commissioning for an industrial cobalt-60 gamma-radiation facility |
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Institution: | 1. Physics Department ICEN/LNETI P.O. Box 21, 2686 Sacavém Codex, Portugal;2. Institute of Isotopes of the Hungarian Academy of Sciences, H-1525 Budapest, P.O. Box 77, Hungary;1. Department of Biological Engineering, Biohybrid Systems Research Center (BSRC), Inha University, 100 Inha-ro, Incheon 22212, Republic of Korea;2. Department of Energy and Materials Engineering, Dongguk University-Seoul, 30 Pildong-ro 1-gil, Seoul 04620, Republic of Korea;3. Biotechnology Research Division, Advanced Radiation Technology Institute (ARTI), Korea Atomic Energy Research Institute (KAERI), 29 Geumgu-gil, Jeongeup, Jeonbuk 56212, Republic of Korea;4. Radiation Biotechnology and Applied Radioisotope Science, University of Science Technology (UST), 217 Gajeong-ro, Daejeon 34113, Republic of Korea;5. WCSL of Integrated Human Airway-on-a-Chip, Inha University, 100 Inha-ro, Incheon 22212, Republic of Korea;1. Medical Physics Unit, University of Malaya Medical Centre, Lembah Pantai, 59100 Kuala Lumpur, Malaysia;2. Clinical Oncology Unit, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur, Malaysia;3. Department of Biomedical Imaging, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur, Malaysia;4. Department of Human Anatomy, Faculty of Medicine and Health Sciences, Universiti Putra Malaysia, 43400 Serdang, Malaysia;1. Radiation Physics, Materials Technology and Biomedical Imaging Laboratory, Department of Biomedical Engineering, Technological Educational Institute of Athens, Egaleo, 122 10 Athens, Greece;2. Faculty of Chemistry, Wroclaw University, 14F Joliot-Curie Street, 50-383 Wroclaw, Poland;1. Department of Radiology, Jichi Medical University, Tochigi, Japan;2. Department of Radiation Oncology, Saitama Medical University International Medical Center, Saitama, Japan;3. Department of Radiation Oncology, Gunma University Graduate School of Medicine, Gunma, Japan;4. Department of Radiation Oncology, Delta Hospital Limited, Dhaka, Bangladesh;6. Department of General Radiation Oncology, National Cancer Hospital, Hanoi, Vietnam;5. Department of Radiation Oncology, National Cancer Center of Mongolia, Ulaanbaatar, Mongolia;7. Department of Radiotherapy, Dr. Cipto Mangunkusumo General Hospital - Faculty of Medicine, Universitas Indonesia, Jakarta, Indonesia;11. Department of Radiation Oncology, First Affiliated Hospital of Soochow University, Suzhou, China;12. Department of Radiation Oncology, Sarawak General Hospital, Kuching, Malaysia;8. Department of Radiation Oncology, St Luke''s Medical Center, Quezon City, Philippines;10. Department of Radiology, Faculty of Medicine, Siriraj Hospital, Mahidol University, Bangkok, Thailand;9. Department of Radiation Oncology, Korea Institute of Radiological and Medical Sciences, Seoul, Korea;71. Department of Oncology and Visual Diagnostics, Semey State Medical University, Semey, Kazakhstan;112. National Institute of Radiological Sciences Hospital, National Institutes for Quantum and Radiological Science and Technology, Chiba, Japan |
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Abstract: | In order to establish plant operational parameters of the industrial 60Co irradiation facility, UTR GAMA-Pi, a commissioning dosimetry procedure was carried out at the National Laboratory for Engineering and Industrial Technology (LNETI), Lisbon, Portugal. Detailed dose mapping, with and without industrial product, was used to measure the distribution of absorbed dose in the radiation field inside the irradiation cell. “Dummy” and “dosimetry” boxes were prepared, each having 200 kg m−3 bulk density, using a combination of cardboard sheets and folded and crumpled newspapers. Four dosimeter systems were used for measurements: red and amber Perspex, radiochromic dye films, ethanol-monochlorobenzene solutions and potassium dichromate solutions. All systems were calibrated against the Fricke dosimeter solution. The dosimetry commissioning procedures allowed the establishment of the setting of conveyor dwell times to reach prescribed minimum doses, as well as the computation of a source utilization efficiency of approx. 19.5% and a dose uniformity ratio of approx. 1.25. Using these data, the capacity throughput of the irradiation plant was evaluated to be 4265 m3 yr−1 or 853 tonnes yr−1 for the 60Co plaque source with an initial activity of 1.095 × 1016 Bq (295 kCi) (November 1988), at an operational working time of 7000 h yr−1, and a specified product dwell time setting of 12.6 min, for a minimum absorbed dose of 25 kGy and a product bulk density of 200 kg m−3. |
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