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Design and Analysis of Hot Cell Shielding Thickness for Dismantling of High Activity Disused Sealed Radioactive Sources to Support Decision Making

Not scheduled
20m
M-Building (IAEA Headquarters, Vienna)

M-Building

IAEA Headquarters, Vienna

Vienna International Center - Wagramer Str 5 - PO Box 100, 1400 Vienna, Austria
POSTER Track 5 - Practical experiences in integrating safety and sustainable development

Speaker

Mr Adi Wijayanto (Radioactive Waste Management Installation - Directorate of Nuclear Facilities Management - National Research and Innovation Agency (BRIN))

Description

The National Research and Innovation Agency of Indonesia has a facility called the Radioactive Waste Management Installation (RWMI). RWMI handles radioactive waste from industries and hospitals, with a particular focus on Disused Sealed Radioactive Sources (DSRS) in Indonesia. RWMI is highly concerned about the safety aspects of workers in the radioactive waste processing installation. One of the facilities at RWMI is a hot cell, which is a specially designed room used to confine radioactive waste sources. It is equipped with manipulators for handling high-activity and high-radiation-exposure radioactive substances from a safe distance. To ensure the safety of radiation workers, the hot cell will be revitalized to enable the handling of high-level radioactive waste in categories 1 and 2. As part of this revitalization process, an analysis of effective shielding material thickness is needed for radiation protection. Therefore, a simulation was carried out using Microshield 7 software to obtain the dose rate received by workers at several points. For the simulation scenario, a cylindrical Cobalt-60 source with a maximum activity of 15,000 Ci was selected. The results showed that the thicker the shielding material and the farther the radiation workers are from the hot cell, the lower the exposure they receive. The most effective and suitable material obtained for use is high-density concrete (3.2 g/cc) because if this material is used, radiation workers at the closest distance will receive a low enough exposure below 100 μSv/h. Besides being effective as a radiation shield, this material is relatively inexpensive and easy to obtain in Indonesia compared to lead glass, which is also a good radiation shielding material. In addition, this material has a price that is still affordable than lead glass material which can reach hundreds of thousands to millions of rupiah.

Primary author

Mr Adi Wijayanto (Radioactive Waste Management Installation - Directorate of Nuclear Facilities Management - National Research and Innovation Agency (BRIN))

Co-authors

Ms Titik Sundari (Radioactive Waste Management Installation - Directorate of Nuclear Facilities Management - National Research and Innovation Agency (BRIN)) Mr Rajendra Satriya Utama (Department of Nuclear and Physics Engineering Gadjah Mada University (UGM))

Presentation materials

Proceedings

Paper