Studies on sodium aerosols dispersion in open environment for fast reactor safety by Subramanian, V., Kumar, Amit, Pujala, Usha, Sujatha, P.N., Srinivas, C. Venkata, Bagavathsingh, A., Goplakrishnan, V., Ananthanarayanan, R., Kumar, A. Ashok, Kumar, S. Krishna, Chandramouli, S., Baskaran, R., Nashine, B.K., Venkatraman, B.

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Waste-polymer incorporated concrete mixes for neutron and gamma radiation shielding by Malkapur, Santhosh M., Ghodke, Shobha S., Sujatha, P.N., Singh, Yashoda, Shivakumar, K.S., Sen, Meghanath, Narasimhan, Mattur C., Pulgur, Abhishek V.

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Experimental studies on morphological properties of sodium combustion, fission product, structural material and mixed aerosols in a closed chamber towards fast reactor safety by Pujala, Usha, Kumar, Amit, P.N., Sujatha, V., Subramanian, C.V., Srinivas, R., Baskaran

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Development of a portable transfer standard for the neutron source yield measurement using Fluka simulation by Sen, Meghnath, Sathian, V., Shobha, G., Sujatha, P.N., Yashoda, S., Kulkarni, M.S., Babu, D.A.R.

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Spectrum of mutations in the ATP binding domain of ATP7B gene of Wilson Disease in a regional Indian cohort by Guggilla, Sreenivasa Rao, Senagari, Jalandhar Reddy, Rao, P.N., Madireddi, Sujatha

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