Speaker
Description
Scope
This study describe the safe and secure transport of two (cat. 2) Tele-therapy devises (Phoenix, T780C), which contained Depleted Uranium (DU) used as shielding material and have previously been applied for cancer treatment. The project describes the complete processes, from preparation of heads to their successful delivery to Hungary.
Background
This project is very important to Jordan, providing new experience in the field of transporting radioactive sources to abroad. It aims to gain practical experience in this field, in addition to enhancing efficiency and skills for operators.
Objectives
1. Ensuring safety of radioactive sources with high activity.
2. Protecting environment and future generation.
3. Reducing the volume of radioactive materials stored at CSF
4. Promoting the use of new technology in medical treatment
Methodology
According to the national policy and strategy for radioactive waste & spent nuclear fuel management, a permit was granted to transport these sources to another country, in accordance with the regulations and instructions in Jordan issued by Energy and Minerals Regulatory Commission (EMRC) including:
1. Regulations on the Transport of Radioactive Materials, No. (32) and its Instructions, 2016.
2. National Policy for Radioactive Waste & Spent Nuclear Fuel Management, 2015.
3. Instructions on the Management of Radioactive Waste, 2015.
4. Law of Radiation Protection, & Nuclear Safety & Security No. (43), 2007.
5. Regulation of Radiation Protection No. (108) and its Instructions, 2015.
The priority was to precisely define the roles and responsibilities of the relevant parties and develop clear plans to facilitate the process. Jordan Atomic Energy Commission (JAEC) is responsible for implementing the plans related to transport, safety and security, while the Transport and Radioactive Waste Management Directorate was responsible for preparing for transport and storage of sources at the central storage facility (CSF). All plans were approved by EMRC.
• Prepare the sources inside CSF and receive the empty type B(U) packages from Hungary.
• Place the sources in the packages inside the facility according to safety and preparation procedures.
• Perform accurate dose rate measurements, check for surface contamination, and ensure package labeling.
• Transport the packages to the airport according to a specified schedule and safe routes.
• Repeat all safety-related procedures.
• Ship the packages to Hungary.
The IAEA supported the project through a dedicated international fund. The warhead removal process was carried out by a licensed and professional service provider under IAEA Contract No. 202204058. It should be noted that the (DU) material was handled according to established procedures and reported to the International Atomic Energy Agency (IAEA) nuclear safeguards department
Conclusion
Throughout the operation, the Radiation Protection Officer (RPO) controlled and monitored the entire process. The measured dose rate at the surface of each devise were less than 11 µSv/h. The occupational exposure of workers involved in the project did not exceed 5 µSv, and no radiological contamination was detected during the mission.
No incidents or accidents occurred during the project's implementation and the packages arrived safely in Hungary and all activities were completed according to the schedule, despite the challenges associated with the high risk cross border transport. This participatory experience provided valuable experience and lessons learned that can support other countries in managing similar operations involving high-activity radioactive sources and nuclear material transport.
