Kusuma Tongsukh. Monitoring of radioiodine-131 contamination in the sewage system of Siriraj Hospital. Master's Degree(Radiological Science). Mahidol University. Mahidol University Library and Knowledge Center. : Mahidol University, 2009.
Monitoring of radioiodine-131 contamination in the sewage system of Siriraj Hospital
Abstract:
Therapeutic application of radioiodine (I-131) for the treatment of thyroid cancer
results in a significant volume of contaminated liquid discharges into the hospital wastewater
treatment system. This study aims to measure radioactivity concentration of I-131 in the
liquid, before and after wastewater treatment, and to estimate radiation dose to the public who
may be exposed after the point of disposal. This study also measured external radiation dose
rates in the public areas utilizing recycled water and in the wastewater treatment plant areas to
determine radiation dose rates that may be encountered by the plant workers.
The mean (SD) of I-131 radioactivities in pretreated wastewater samples was 23.99
(57.86) Bq/ml. After wastewater treatment, the radioactivity concentration of I-131 in the
effluents and recycle effluents of 0.29 and 0.30 Bq/ml was approximately 1.2% of the
pretreated radioactivity concentration (p<0.05). At this radioactivity concentration level, the
liquid waste release was approximately 7 times higher than the clearance level for liquid
release of 0.04 Bq/ml allowed by the Regulatory Authority (p<0.05). However, an estimated
radiation dose of 0.09 μSv per year is the most likely to be received by members of the public
as a consequence of the release of liquid effluents to the environment and does not exceed the
annual radiation dose limit of 1000 μSv, as recommended by the International Atomic Energy
Agency Basic Safety Standards (IAEA BSS). The measure of external radiation dose rates
averaged 0.16 to 0.17 μSv/h in areas that utilized recycled water and in the wastewater
treatment plant areas, although approximately 1.20 times greater than the background
radiation control areas (p<0.05), it was much lower than the 20 μSv allowed in any one hours
limit for an external radiation dose in an uncontrolled area. By direct measurement using
electronic dosimeter, the plant workers received radiation dose was 125 μSv per year. This is
higher than an annual radiation dose constraint of 100 μSv but lower than annual radiation
dose limits for a member of the public.
In conclusion, the discharge of liquid effluents into the river and the surveillance
performed in this study demonstrated compliance with the radiation dose limits of the IAEA
BSS. The radiation dose received both from external radiation and from the release to the
surface water environment is too low to contribute to health problems in the public involved.