Characterization of novel SeTeSn Chalcogenide Glassy Alloy (STS ChGA) as shielding material: Case study of its resistance against γ-ray irradiation for nuclear waste immobilization applications

Abstract

Intense investigations are in progress globally towards the immobilization of radioactive and non-radioactive nuclear waste by their direct vitrification or by using novel glassy materials as an alternate shield. In fact, the entire technologies and economies of nuclear waste immobilization have been envisaged in the future on the basis of these approaches. Use of the glassy materials for shielding purpose is an important step towards realizing this vision. The radiation-induced effects of γ-ray irradiation (60Co source, 4 kGy, 8kGy and 12 kGy doses) have been examined in a novel STS ChGA. The physicochemical properties of present STS ChGA have been compared before and after γ-ray irradiation. Analysis of the different properties reveals the non-linear and non-monotonic behavior with increase in the dose of γ-ray irradiation but it suggests the possibilities of the application of this novel material for radiation shielding. In view of practical application in nuclear waste immobilization, the present finding reveals the possibilities for development of innovative ChGA based shielding system with stable and controlled parameters (like thermal stability, glass forming ability, crystallization rate, hardness etc). An attempt has been also made for understanding the mechanisms of radiation-induced effects in the present study.