Post closure safety assessment for near surface disposal
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Near-surface facilities which are designed on or below the surface are typically used for Low Level Waste (LLW) and short-lived Intermediate Level Waste (ILW) disposal. Due to the site characteristics changes such as climate in the long-term period, a comprehensive disposal Safety Assessment (SA) is required to predict the future situation. The main aim of this paper is to make a safety assessment of a trench type near surface disposal facility in Iran based on ISAM methodology recommended by the International Atomic Energy Agency (IAEA). In such a manner, a surface water erosion, a shepherd, and a human intrusion are considered as design and alternative scenarios to model using AMBER code for a period of 100,000 years. Results presented; the maximum radiation is related to human intrusion scenario in which the total dose radiation reached to 0.3 mSv/y in the first year after the site passive institutional control. Moreover, the dose released from the investigated scenarios in the postclosure phase was less than 1 mSv/y, which is the IAEA regulatory body safety criteria. Comparison of the results showed that the current site is designed and constructed in accordance with safety guidelines which are established by the IAEA and Iran National Regulatory Authority (INRA).
Abstract
Near-surface facilities which are designed on or below the surface are typically used for Low Level Waste (LLW) and short-lived Intermediate Level Waste (ILW) disposal. Due to the site characteristics changes such as climate in the long-term period, a comprehensive disposal Safety Assessment (SA) is required to predict the future situation. The main aim of this paper is to make a safety assessment of a trench type near surface disposal facility in Iran based on ISAM methodology recommended by the International Atomic Energy Agency (IAEA). In such a manner, a surface water erosion, a shepherd, and a human intrusion are considered as design and alternative scenarios to model using AMBER code for a period of 100,000 years. Results presented; the maximum radiation is related to human intrusion scenario in which the total dose radiation reached to 0.3 mSv/y in the first year after the site passive institutional control. Moreover, the dose released from the investigated scenarios in the postclosure phase was less than 1 mSv/y, which is the IAEA regulatory body safety criteria. Comparison of the results showed that the current site is designed and constructed in accordance with safety guidelines which are established by the IAEA and Iran National Regulatory Authority (INRA).