Assessing the performance of a novel Fe-based material for replacement of Co-based alloy Stellite in CANDU reactor components

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H. Ha
Heidi Nordin

Abstract

Activation of 59Co to form radioactive 60Co in the primary heat transport system (PHTS) of CANDU reactors has been identified as one of the main source terms of gamma radiation to workers. In the CANDU PHTS, 59Co is present as particulates and dissolved species resulting from wear and corrosion of Co-containing components, such as valves as for light water reactors but also fueling machine bearing balls made of Co-based alloys like Stellite. Therefore, replacing Co-based alloy components in the PHTS with Co-free materials has been proposed as one of the strategies to reduce worker dose. A novel Fe-based alloy with a composition of Fe-25Cr-4Ni-2Mo-0.4N manufactured by hot-isostatic-press is a promising candidate for Stellite replacement. Corrosion and mechanical testing of the Fe-based alloy under conditions relevant to the operation of CANDU fueling machine was performed. Potentiodynamic polarization and long-term immersion tests in refreshed autoclaves showed that the Fe-based alloy exhibited corrosion resistance equivalent to or better than Stellite 6 in aerated lithiated water at temperatures up to 300 °C. Additionally, the performance of the Fe-based alloy in uniaxial compression tests conducted on ball samples in air at room temperature, 150 °C, and 300 °C showed similar behavior to Stellite 6.

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