FAST BREEDER TEST REACTOR

The feasibility of the design, construction and operation of FBRs under Indian conditions has been proven by the successful construction and commissioning of Fast Breeder Test Reactor [FBTR], a 40 MWt/ 13.2 MWe, loop type reactor using sodium as coolant. Though the basic design is based on the French reactor "RAPSODIE", several modifications including addition of steam generators for power generation were made to suit our requirements. It uses a unique Plutonium-Uranium mixed carbide fuel developed indigenously. The fuel has achieved a burn-up of 40000 MWd/t (as on Oct. 1997); there has been no fuel pin failure so far. FBTR has reached an important milestone, when it was synchronized with the southern grid for the first time on 11th July 1997, thus establishing the indigenous capability for generating electricity through FBRs. The reactor is mainly used as a test-bed for irradiation experiments on fuels and other reactor materials. 

CHARACTERISTICS

REACTOR COOLANT
PRIMARY CIRCUIT CONCEPT
THERMAL POWER
ELECTRICAL POWER  
FUEL 
CORE HEIGHT 
ODIUM INLET TEMPERATURES
SODIUM OUTLET TEMPERATURE
SODIUM INVENTORY 
STEAM CONDITIONS AT TURBINE INLET
CONTROL RODS
NEUTRON FLUX

 : SODIUM  
 : LOOP
 : 40 MWt 
 : 13.2 MWe
 : 70 % PUC-30 % UC [MARK I core]
 : 320 mm
 : 380 deg.C
 : 515 deg.C
 : 150 TONNES
 : 490 deg.C at 167 BAR
 : 6 NOS. OF BORON CARBIDE
 : 3 X 10 15 n/sq.cm/sec 

fbtr.jpg (103796 bytes)  

MILESTONES ACHIEVED

18th OCTOBER 1985
1989-92
MARCH 1993
DECEMBER 1993
11th JULY 1997
: FIRST CRITICALITY
: OPERATION AT 1MWt
: POWER RAISED TO 10.5 MWt
: 1.6 ATOM % BURN UP ACHIEVED WITHOUT FUEL FAILURE
: SYNCHRONIZATION WITH SOUTHERN GRID