Avinash Jagannath Gaikwad

Avinash Jagannath Gaikwad received the B.E. degree (first degree) in chemical engineering from Pune University, 1987. Presently, he is working as a Scientific Officer (SO/G), in CSSS ,Reactor Safety Division (RSD). His publications include 3 journals, 23 international and 32 national, total 58 papers, more than 57 reports for NPCIL and AHWR design group. Gaikwad has been working on the development of process dynamics simulation computer codes (based on mathematical models) and using RELAP5/MOD3.2 code for nuclear power plant safety and transient analysis. These simulation models are based on unsteady state mass, momentum, and equation of state for fluid with heat transfer packages. This work also includes generating design feedbacks, process optimization parametric studies, developing the associated control system models, and advanced process controller concepts/development. Computer simulation code Dyna540 was developed for 540 MWe nuclear power plant pressurised heavy water reactor (PHWR). 700 MWe PHWR & AHWR, that is, advanced heavy water reactor, simulation models were developed using RELAP5/MOD3.2. His projects and tasks include 540 MWe PHWR power plant operational transient analysis code Dyna540 development used for surge line sizing, selection of steam generator pressure control (SGPC) program, pressuriser level selection, IRVs design basis transient, steam bleed valve stuck open malfunction, IRVs stuck open, one PCP trip, station blackout, ans so on; 750 MWe advanced heavy water boiling water reactor (AHWR) RELAP5/MOD3.2 simulation, steam drum model, drum pressure and level controller, turbine trip, reactor trip, ICs cooling, and so on; 700 MWe PHWR simulation model development using RELAP5 for PHT, Pressuriser, and SGs; 700 MWe PHWR passive decay heat pemoval (PDHR) system simulation model for design verification studies with boil off; and 700 MWe PHWR station blackout analysis with PDHR and steam line break analysis.

Biography Updated on 21 June 2007

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