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Apr 19 – 22, 2022
Vienna, Austria
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Design Studies Towards Raising FBTR to Full Power

Apr 20, 2022, 11:52 AM
Vienna, Austria

Vienna, Austria

ORAL Track 2. Fast Reactor Safety 2.2 Safety Design and Analysis


RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam)


Fast Breeder Test Reactor (FBTR) is a loop type sodium cooled fast reactor, operating at Kalpakkam. FBTR core is originally designed to operate at 40 MWt using mixed oxide (MOX) fuel with 30% PuO2 and 70% UO2 (85% enriched U). However, due to the non-availability of enriched uranium, mixed carbide fuel (Mark-I (70% PuC+30%UC)) was chosen for the initial core. After first criticality in 1985, the initial core had operated with a maximum power of 10.6 MWt. Subsequent operations have been carried out by adding many variants of carbide and oxide fuel sub-assemblies (FSAs) and increasing the operating linear heat rating (LHR) in stages, based on the encouraging post irradiation examination (PIE) results. The plant is operating at the power level of 32 MWt during its 29th campaign.
It is planned to raise the power of FBTR to its design target power of 40 MWt by using Mark-I subassemblies (SAs). The transition to 40 MWt core is proposed to be taken up during the 30th campaign. The envisaged core will have 70 fuel SAs and the peak LHR will remain restricted at 400 W/cm. In order to ensure a minimum shutdown margin of 4200 pcm as per the technical specification for operation, four poison SAs (with 50% B-10 enrichment) are added in the second ring along with existing 6 control rod SAs (B-10 enrichment of 90 %) provided in the 4th ring. The core design studies have been completed.
Safety studies of the 40 MWt core have been carried out and perturbation worths & kinetic parameters have been estimated. Hypothetical Core Disruptive Accidents (HCDA) have been analysed for ULOFA, ULOCA and UTOPA. For this core, 12 MJ can be considered as the maximum possible mechanical energy release under HCDA. In order to demonstrate the inherent safety characteristics and the capability of plant protection system with respect to various plant transients, analyses of various enveloping design basis events have been carried out using the plant dynamics code DYNAM and safety is demonstrated. Detectable and permissible flow reduction for different SAs has been estimated and found to be safe. Shielding analysis show that in general, there is an increase in neutron and gamma fluxes at various locations of core and shield regions with respect to the 32MWt core. This paper summarises the studies carried out towards raising the power of FBTR to 40 MWt.

Country/Int. organization India
Speaker's title Mr
Affiliation/Organization Indira Gandhi Centre for Atomic Research, Kalpakkam
Speaker's email address

Primary authors

RAGHUPATHY S. (Indira Gandhi Centre for Atomic Research, Kalpakkam) Mr Devan R (IGCAR) Mr Arul John (IGCAR) Mr Natesan K (IGCAR) Mr Srinivasan G.S. (IGCAR) Mr Naga Sivayya D (IGCAR) Mr Anuraj V.L (IGCAR) Mr Sunil Kumar D (IGCAR) Mr Niraj Ganesh Janwade (IGCAR)

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