Chandrakant Pithawa


Day 2(28th October)-3:00 PM

Venue-ECE Seminar Hall

Contact Details

ABSR Sateesh
Aabha Chandra
Mayank Kumar
Somesh Kumar
Rishu Kumar

PadmaShri. Chandrakant Pithawa, is retired distinguished Scientist and Director, Electronics & Instrumentation Group at BARC, Trombay, Mumbai. At present Mr.Pithawa is Raja Ramanna Fellow, ECIL, Hyderabad. He completed his ME Automation from IISC Bangalore & MS Electronics from University of Southampton UK. His professional experience include: Head, Computer Control Design Section, Reactor Control Division, BARC; Additional Director, Design Manufacturing & Automation Group, BARC. Pithawa's areas of interest include: Computer based embedded control systems for critical applications, Nuclear instrumentation, Nuclear Radiation Detectors and Instruments, EMP Protections. His major professional contribution include: Computer based embedded control systems for Kaiga-1&2, RAPP-3&4 and TAPP-3&4 nuclear power plants, Dhruva Research Reactor and High Temperature Fission Detectors & Ultrasonic camera for under sodium scanning for PFBR, Servo Control systems and Gamma camera Electronics for large MACE telescope, Computer based control systems for many other critical applications.

Mr.Pithawa is honored with the fourth highest civilian award PadmaShri, by the Government of India for his outstanding contribution in the field of science & technology. His other Awards and Major Professional Recognitions include:  DAE (Department of Atomic Energy) Special Contribution Award, Five numbers of DAE Group Achievement Awards for Excellence in Science Engineering and Technology, Outstanding Service Award of Indian Nuclear Society.

The title of the keynote lecture is: "Instrumentation & Control for Nuclear Power Generating Plants and Indian Scenario".

Instrumentation and Control systems performing functions important to safety in a nuclear power generating plant not only have to meet the functional, performance and interface requirements but must also be demonstrated to be safe and reliable with appropriate degree of confidence.

The talk will cover the practice of design and implementation of computer based systems for carrying out functions important to safety for the nuclear power generating plant and will explain the same with a case study.