Saratchandran, N and Garg, R K and Sundaram, C V and Katiyar, H C (1969) The present status and the projected programme of Zirconium development in India. In: Symposium on Non-ferrous Metals Technology. Symposium on Non-ferrous Metals Technology, Volume III - Nickel, Lead, Zinc, Rare earth and Nuclear Metals . NML, Jamshedpur, Jamshedpur, pp. 1-10.
THE nuclear power industry continues to be the major consumer of zirconium metal production in the world today. On the basis of neutron economy, corrosion resistance and mechanical strength, zirconium alloys have been the ideal choice for the fuel-cladding and other core components in watercooled nuclear power systems. In the United States alone, the current annual requirement of zircaloy tubing for nuclear fuel cladding has been placed at 250 tons, which will grow to 600 tons by 1970 and 900 tons by 1973. In India, for the 1200 MW(e) nuclear power programme envisaged for the IV Plan period, zircaloy tube requir-ements have been estimated at 50 tons per year and will increase to 75 tons and more during the V Plan period.
|Item Type:||Book or NML Publication|
|Uncontrolled Keywords:||Zirconium, Corrosion resistance, Neutron economy|
|Divisions:||Metal Extraction and Forming|
|Deposited By:||Sahu A K|
|Deposited On:||13 Sep 2011 13:37|
|Last Modified:||06 Jan 2012 11:55|
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