U
U. Kamachi Mudali
Researcher at Indira Gandhi Centre for Atomic Research
Publications - 422
Citations - 8467
U. Kamachi Mudali is an academic researcher from Indira Gandhi Centre for Atomic Research. The author has contributed to research in topics: Corrosion & Nitric acid. The author has an hindex of 38, co-authored 419 publications receiving 7010 citations. Previous affiliations of U. Kamachi Mudali include Indian Department of Atomic Energy & University of Madras.
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Dissimilar Joining of Zircaloy-4 to Type 304L Stainless Steel by Friction Welding Process
A. Ravi Shankar,S. Suresh Babu,Mohammed Ashfaq,U. Kamachi Mudali,K. Prasad Rao,N. Saibaba,Baldev Raj +6 more
TL;DR: In this article, a solid-state joining process of friction welding was proposed to join zircaloy-4 and type 304L stainless steel (SS), which required high integrity and corrosion resistant dissimilar joints.
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Sensitization and Intergranular Corrosion Behavior of High Nitrogen Type 304LN Stainless Steels for Reprocessing and Waste Management Applications
TL;DR: In this article, vanadium-added 304LN stainless steels (SS) were evaluated for their sensitization and intergranular corrosion (IGC) resistance, and the degree of sensitization was estimated with the double loop electrochemical potentiokinetic reactivation technique.
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In vitro corrosion evaluation of nitrogen ion implanted titanium in simulated body fluid
TL;DR: In this paper, surface modification of commercially pure (CP) titanium was attempted by nitrogen ion implantation to investigate corrosion resistance in simulated body fluid, and nitrogen ion was implanted at 70 keV energy for different doses ranging from 5 × 1015 to 2.5 × 1017 ions/cm2.
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Modeling of Hydrodynamics in a 25 mm ϕ Pulsed Disk and Doughnut Column
TL;DR: In this paper, the experimental data for dispersed phase holdup and flooding throughput has been modelled using the Van Delden model to describe the hydrodynamics characteristics of a pulsed disk and doughnut column (PDDC), and necessary adjustable parameters for drop size distribution and dispersed phase Holdup are updated for 30% TBP-nitric acid system.
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Process Development for Fabrication of Zircaloy-4 Dissolver Assembly for Reprocessing of Spent Nuclear Fuel
TL;DR: In this article, a dissolver assembly for spent fuel reprocessing for Fast Breeder Reactor (FBR) can be manufactured from Zircaloy-4 on an industrial scale, with long life expectancy with near zero corrosion, employing EB and TIG welding processes.