Abstract
Fast Breeder Test Reactor (FBTR) is a 40MWt 13MWe , mixed carbide fueled, sodium cooled, loop type reactor built at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam. The Reactor Vessel (RV) is manufactured using modified AISI 316 austenitic stainless steel material as per FBTR specification. The acceptance criteria for non-destructive examination, quality of weld, test requirement, tolerances on various dimensions etc. specified in FBTR specification are very stringent compared to ASME Section III, Div. I, Class I components and other international codes applicable to pressure vessels and nuclear power plant components. During the manufacture and inspection of the Reactor Vessel, a systematic approach has been adopted towards the improvement of various procedures to achieve very high reliability of the Reactor Vessel. This paper explains the details of results achieved on fabrication tolerances, destructive and non-destructive testing on materials and welds and final tests on the reactor vessel.
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