Centrifugal Pumps for Sodium Cooled Reactors (PDF)

Mr. R.D Kale graduated in Mechanical Engineering from the Indian Institute of Technology (IIT), Kanpur, in 1966. He completed a one-year orientation course in Nuclear Science and Engineering as part of the 10th batch of the Training school at the Bhabha Atomic Research Centre and started his career in BARC. He was deputed to CEN deCadarache, France, where he worked along with French specialists as part of the Indian design team for the design Fast Breeder Test Reactor under a collaborative project with the French atomic energy establishment from May 1969 to June 1970. He moved to the Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, in 1971 and worked for a few years initially on the detailed design of some reactor components and preparation of their technical specifications. He spent the next 28 years establishing water and sodium test facilities to test fast reactor components. These included a large sodium test facility in a 43 m high building for testing full-scale reactor components in sodium and later a dedicated Steam Generator Test Facility for testing a sector prototype of the once-through sodium/water steam generator of the 500 MWe sodium cooled power plant. He spearheaded the indigenous development of sodium centrifugal pumps for the Prototype Fast Breeder Reactor (PFBR) that culminated in the manufacture of both the primary and secondary centrifugal pumps by the Indian industry. He has several publications in reputed journals, seminars, and international conferences. He has published many articles in newspapers on nuclear power and safety. He retired in the grade of Outstanding Scientist. He was the Associate Director of the Engineering Development Group and Director of the Engineering Services Group at the time of superannuation. He has also authored a book in Marathi titled "Adhunic Hindu Dharma, Kaani Kasa?" translated as "Modern Hinduism, Why and How?". In press, his recent book in Hindi is titled "Meri Yatra, 1857 kaAnkhoDekha Hal,"