FBTR passes 53-day continuous operation test

By R. Prasad

CHENNAI, MARCH 21. The Kalpakkam-based Indira Gandhi Centre for Atomic Research (IGCAR) achieved a major milestone when the fast- breeder test reactor (FBTR) was synchronised with the Tamil Nadu grid and was in continuous operation at full power capacity for 53 days from October 28 to December 21, 2000. It was actually synchronised with the grid on October 6, 2000 and was in operation on and off till February 4, 2001. Nearly 7.4 lakh units of electrical energy were generated during the 53 days of continuous operation.

Speaking to TheHindu on its achievement, Mr. R. P. Kapoor, Associate Director, Reactor Operation & Maintenance Group, IGCAR, said the fast-breeder technology developed indigenously was put to test for power generation and it demonstrated the ability to operate in a sustained manner when connected to the grid. This has been the first time that the reactor, steam supply system, turbine generation system and its auxiliaries have worked continuously at full capacity for 53 days. During the first synchronisation with the grid in 1997 the reactor was in continuous operation only for 12 days.

``Running continuously for 53 days at full power capacity has boosted our confidence to go in for the prototype fast-breeder reactor. We can now be assured that all systems connected to the turbine and generator are functioning satisfactorily,'' said Mr. Kapoor. ``And we can now come up with optimal design to get an economically workable reactor based on the feedback from this test run.''

The achievement gains special significance considering the fact that the fuel - mixture of plutonium carbide and uranium carbide - is a unique mixture used for the first time in the world and was developed indigenously.

The grid synchronisation and the continuous run comes in the wake of IGCAR preparing itself for the likelihood of starting the construction of the fast-breeker nuclear power plant prototype by the end of this year.

Fast-breeder reactor is a second-generation technology and uses plutonium (Pu-239) produced in the first-generation pressurised heavy-water reactors. The fast-breeder reactor in turn is a crucial link in converting the naturally occurring thorium (Th- 232) to uranium (U-233) fuel for the third-generation reactors.

India has one of the largest reserves of thorium in the world and third-generation reactors using U-233 are capable of producing nearly five times the coal equivalent in terms of energy produced in the country.

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