Indian Welding Journal

V. Anandkumar ¹, E. Venkatesan ¹, Baldev Raj ¹, C. Karthikeyan ², R. S. Babu ²

Affiliations
1 Indira Gandhi Centre for Atomic Research, Kalpakkam, IN
2 The Welding Research Institute, BHEL, Tiruchirapalli, IN

Abstract

Steam generators are critical components for the Prototype fast Breeder Reactor being designed at the Indira Gandhi Centre for Atomic Research, Kalpakkam. A leak in the steam generators can have serious consequences leading to rupture of steam generator tubes. Consequently, by introducing a known leak in the experimental loop, data is required to be generated which can predict the response of the material to the leak as a function of leak rate, time, temperature, steam pressure and the size of the microhole as a result of sodium water reaction.

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