Decommissioning is the final stage of a nuclear reactor. In preparing the decommissioning plan, one of the important elements that need to be considered is safety assessment. During decommissioning, there are many complex tasks to be done where the radiological and non-radiological hazards arise and can significantly affect not only the workers but also the general public and the environment. Indonesia has no experience with nuclear reactor decommissioning, so it is necessary to study various experiences of decommissioning activities in the world. This study proposes a framework to implement the safety assessment on the decommissioning of the TRIGA 2000 research reactor. The framework was developed on desk-based research and analysis. The proposed framework involves the facility and decommissioning activities, hazard identification, hazard analysis, hazard evaluation, hazard or risk control, and independent review.

RISK MANAGEMENT of Industrial Radiography Personnel Certification Activities to Ensure Worker Safety and Health. The increasing use of radioactive substances and other radiation sources in the Indonesian industry for non-destructive testing lead to a rise in the need for radiographers. In carrying out certification activities, NQSC utilizes radioactive sources in the form of gamma rays from X-ray appliances. Therefore adequate risk management to ensure the safety and health of participants is needed. The risk management process carried out by PSMN uses the hierarchy principle at ISO 45001 and other preventive measures regulated in the IAEA Safety Guidelines, with the measures evaluated periodically using dose reading data. The dosage results on workers and examinees showed that the dose value is below the allowable value with a Dose Limit Value (NBD) of no more than 20 mSv per year. This means that the risk management measures guarantee worker safety and health in the certification activities of industrial radiography personnel in PSMN.

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The G.A. Siwabessy Multipurpose Reactor (RSG GAS) is a pool‐type research reactor. When the reactor operates, the heat released in the core is removed by the primary cooling system. It is necessary to evaluate this system, because failure can cause worst events such as the melting of reactor fuel and the release of radioactivity to the environment. Due to the possibility of radioactive material releases, safety issues are important to be evaluated. Several studies using event tree analysis (ETA), fuzzy fault tree analysis (FFTA) describe the results quantitatively. The varied educations of operators will provide various responses to quantitative results, and a need to create qualitative results that are simple and easy to understand using bowtie analysis that visualizes the risk scenario. Failure of this system causes loss of coolant accident (LOCA) and loss of flow accident (LOFA). The results show that the relationship between the consequences and causes of the risk occurrence LOCA and LOFA, and the controls used to prevent and reduce the hazard based on safety and emergency system at RSG GAS, can be depicted in a bowtie diagram. The bowtie diagram is simple and easy for an RSG GAS operator to carry out their duties and increase awareness regarding the safety of reactor operations.