Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Fast breeder test reactor. 15 years of operating experience

Suresh Kumar, K.V.; Kapoor, R.P.; Ramalingam, P.V.; Rajendran, B.; Srinivasan, G.; Kasiviswanathan, K.V. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))

Abstract

Fast Breeder Test Reactor (FBTR) is a 40 MWt/13.2 MWe sodium cooled, loop type, mixed carbide-fuelled reactor. Its main aim is to gain experience in the design, construction, and operation of fast reactors including sodium systems and to serve as an irradiation facility for development of fuel and structural materials for future fast reactors. It achieved first criticality in October 1985 with Mark I core (70% PuC - 30% UC). Steam generator was put in service in January 1993 and power was raised to 10.5 MWt in December 1993. Turbine generator was synchronized to the grid in July 1997. The indigenously developed mixed carbide fuel has achieved a peak burnup of 88 000 MWd/t till now at a linear heat rating of 320 W/cm and reactor power of 13.4 MWt without any fuel-clad failure. The paper presents operating and decontamination experience, performance of fuel, steam generator, and sodium circuits, certain unusual occurrences encountered by the plant and various improvements carried out in reactor systems to enhance plant availability. (author)

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key words: availability; burnup extension; coolant loops; kalpakkam lmfbr reactor; mixed carbide fuels; reactor cores; reactor start-up; sodium; steam generators, epithermal reactors; fast reactors; fbr type reactors; fuels; liquid metal cooled reactors; lmfbr type reactors
Reference:
Proceedings of a Technical Meeting held in Cadarache, France 11-15 March 2002
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1405, pp:15-27