A study of radiation dose for the accident condition in the Subcritical Assembly for 99Mo Production (SAMOP) reactor experimental facility has been done. The main purpose of this study is to estimate the radiation dose received by worker as well as society during accident condition in the SAMOP reactor experimental facility. In this study, one of the worst accident scenario that has the highest probability is postulated as one of TRIGA fuel fall down in to the SAMOP reactor core during loading-unloading process. That accident inflicts one of this TRIGA fuel broken and radioactive materials are released. The radiation dose is estimated based on the radioactive source-term from ORIGEN 2.1 computer code calculation. Furthermore, the total effective dose equivalent (TEDE) received by the society is calculated using dispersion model of Hotspot 3.0 computer code. From this study, the total radiation dose received by the radiation worker during this accident condition is 4.5 mSv and the maximum TEDE received by society during this accident condition is 0.031 mSv. This study proves that the radiation dose received by worker as well as society during this accident condition is still below the limit appointed by regulatory body (BAPETEN).

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Yogyakarta Nuclear Area (YNA) is one of BATAN’s nuclear facility that has many nuclear facilities such as nuclear reactor, accelerator, irradiator, and waste management system. Due to nuclear accident is potentially occur, YNA has nuclear emergency response program and there is a preparedness system to support this program. Radiation monitoring system is one of utilization to acquire and record nuclear radiation exposure in the facility and its environment. An Internet of Thing based radiation area monitor was developed to improve the system not only to acquire the radiation exposure, but also to distribute the acquired data to the cloud server through the internet network. The distributed radiation data can be utilized to analyze nuclear emergence potential in the nuclear emergency response and preparedness system. The area monitor system was designed as sensor network that consists of Geiger Muller detector and high voltage power supply, signal conditioning system, and Arduino as counter and data processor. Data is acquired by a detector and it is transmitted to the server through wireless network using the node MCU communication module. The receiver station system was developed to acquire data from database server to display the radiation exposure in the environment and to identify radiological emergency status. Based on the chi square test stability method, the developed device has good stability which the probability of x 2 was obtained 0.75. The validation testing also was done using Sr-90 and x-ray spectrometer as radiation source, and the developed device has been compared using a standard survey-meter. The mean square error of this validation testing was 0.37 and 0.24 respectively for Sr-90 at two difference source distance, while for x-ray spectrometer source the mean square error value was 2.48. For further development, the system will be combined with a smart meteorological system to build the integrated data acquisition system for Nuclear and Radiological Emergency Preparedness System in Yogyakarta Nuclear Area.

A study of the dose curve to determine the dose received by a patient on the diagnostic radiology was carried out. One of the efforts to apply radiation dose optimization in diagnostic radiology is using the Diagnostic Reference Level (DRL), the dose value used as a reference for each radiological examination. The primary purpose of this study is to develop a method for determining the dose curve as a function of two variables: x-ray tube current and x-ray beam energy. Furthermore, the dose curve that has been developed can be used to estimate the value of the patient dose for each exposure factor arranged. In this study, the dose curve is determined using the polynomial model compiled using MATLAB software, and then validation is carried out using calibrated dosimeter. It shows that at a focus-to-detector distance (FDD) of 100 cm, the deviation factor is 4.89%. It meets the acceptance criteria determined, which is less than 5%. Furthermore, another validation result at FFD 50 cm shows that the average deviation value is 0.43%. In addition, the estimated dose still met the DRL criteria, where the estimated dose obtained for thorax AP and abdominal examinations are 0.26 mGy and 1.5 mGy, respectively. These values were still below the Indonesian Diagnostic Reference Level (IDRL) criteria determined by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN), which are 0.4 mGy and 10 mGy for thorax AP and abdominal, respectively.

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