Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Status of fast reactor development in India (April 1996 - March 1997)

Bhoje, S.B. (Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India))

Abstract

India generated 395 TWh of electricity during, 4 April 1996 to March 1997. Oil import bill during the year was $9.3 billion. The operating performance of the thermal power reactors has considerably improved during the year and has enhanced the confidence level in nuclear energy in the government and the public. Construction of 4x220 MWe PHWR is continued at two locations. Start of construction of 2x220 MWe PHWR, 2x500 MWe PHWR and 2x1000 MWe WWER (Russian collaboration) and 500 MWe PFBR have been proposed in the IX Plan (1997- 2002). The 13 party coalition government is discussing the IX plan proposals in the power sector. Operation of FBTR at 10.5 MWt is continued The maximum fuel burnup reached is 32,000 MWd/t without any failure. Targeted burnup is 50,000 MWd/t. Post irradiation examination has been completed on one fuel subassembly taken out at 25,000 MWd/t. The performance of the fuel is very good. Turbine was rolled up to synchronous speed of 3000 rpm several times during the year and operation was found to be smooth. TG synchronisation with grid will be achieved during the reactor operation at 12.5 MWt, with the addition of fuel subassemblies in the core. All the activities related to the revision of conceptual design from 4 loop to 2 loop concept are almost complete for the 500 MWe Prototype Fast Breeder Reactor. The main options for the reactor are sodium coolant, pool type, MOX fuel, 2 primary sodium pumps, 2 secondary loops with 4 SG in each loop. The important design activities carried out during the year are plant dynamic studies, decay heat removal analysis, design of pump to grid plate pipe, scram and LOR parameters, location of secondary sodium pump in the secondary sodium circuit and design of fuel handling machines. Important experimental R and D work carried out during the year were testing of prototype primary sodium pump in water, operation of a large sodium test rig to study the heat and mass transfer in the cover gas, testing of dummy fuel subassembly in water test rig for pressure drop and vibration measurements.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Advances in fast reactor technology. 30-st meeting of the International Working Group on Fast Reactors, Beijing (China). 13-16 May 1997
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1015, pp:79-109