FBR-600

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FBR-600
GenerationGeneration III+ reactor
Reactor conceptPlutonium Fast breeder reactor
Reactor lineIFBR (Indian fast-breeder Reactor)
Designed byIGCAR
Manufactured byBHAVINI
StatusUnder development
Main parameters of the reactor core
Fuel (fissile material)235U/239Pu (NEU/239Pu/MOX)
Fuel stateSolid
Neutron energy spectrumFast
Primary control methodcontrol rods
Primary coolantLiquid Sodium
Reactor usage
Primary useBreeding of 233U for AHWR-300 and Generation of electricity
Power (electric)600

The Fast Breeder Reactor-600 (FBR-600) or Indian Fast Breeder Reactor (IFBR) or Commercial Fast Breeder Reactor (CFBR) is a 600-MWe fast breeder nuclear reactor design presently being designed as part of India's three-stage nuclear power programme to commercialise the Prototype Fast Breeder Reactor built at Kalpakkam. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor as a successor for Prototype Fast Breeder Reactor (PFBR).[1] The 1st twin unit would come up within the BHAVINI premises at Madras Atomic Power Station at Kalpakkam, close to the PFBR site itself.

Designed to "burn" a mixture of uranium oxide and plutonium oxide to generate 600 MWe of power each, current plans involve building six units, co-locating two at any given place. This arrangement would facilitate cost-rationalisation, using common auxiliaries to serve both reactors.[1]

Design features[]

According to the research conducted at IGCAR, the improved design concepts indicated significant economic advantages by reducing material inventory by 25%, simplifying fuel handling scheme and by reducing manufacture time with enhanced safety parameters.

Safety features[]

CFBR designs mentions a new and improved decay heat removal (DHR) system, reactor shutdown system from its predecessor PFBR. Passive safety features include new hydraulically suspended absorber rods (HSAR) which fall into the core under the influence of gravity if coolant flow is lost, and the inclusion of an ultimate shutdown system (USD) which would use pressurized gas to forcefully inject neutron poisons directly into the core to halt re-criticality incidents.[2]

Reactor fleet[]

Power station Operator Location Status Operation start
PFBR (Prototype) BHAVINI Kalpakkam, Tamil Nadu Under commissioning checks 2023 (planned)
FBR-1 Planned
FBR-2 Planned

Technical specifications and comparison[]

Comparison of FBR-600 to Prototype Fast Breeder Reactor (PFBR)
Specifications FBR-600[3][4] PFBR[5][6][7][8]
Thermal output, MWth 1500 1253
Active power, MWe 600 500
Efficiency, net % 40 39.9
Coolant temperature, °C:
  core coolant inlet 397 397
  core coolant outlet 547 547
Primary coolant material liquid sodium liquid sodium
Active core height, cm 100 111
Equivalent core diameter, mm – 1900
Average fuel power density, MW/m3 – 416
Average core power density, MW/m3 – –
Fuel two enrichment zones of 19.9 and 26.5 wt% of PuO2 in the mixture of PuO2 and UO2 two enrichment zones of 20.7 and 27.7 wt% of PuO2 in the mixture of PuO2 and UO2
Cladding tube material – 20% CW D9
Fuel assemblies –
  • 85 of 20.7 % PuO2
  • 96 of 27.7% PuO2,
Number of pins in assembly – 217
Fuel cycle length, Effective Full Power Days (EFPD) 210 250
Average fuel burnup, GWd/t 100 134
Breeding ratio 1.13 1.05
Sodium void coefficient ($) <1
Control rods B4C boron carbide B4C boron carbide
Neutron absorber B4C boron carbide B4C boron carbide

See also[]

References[]

  1. ^ a b "FBR-600 – India's Next-gen Commercial Fast Breeder Reactor [CFBR]". AA Me, IN. 4 October 2015. Retrieved 28 June 2016.
  2. ^ Chellapandi, P.; Rao, P R Vasudeva; Kumar, Prabhat (2015). "Fast reactor programme in India". Pramana. 85 (3): 525–538. Bibcode:2015Prama..85..525C. doi:10.1007/s12043-015-1069-6. S2CID 119688291.
  3. ^ Puthiyavinayagam, P; Selvarj, P; Balasubramaniyan, V; Raghupathy, S; Velusamy, K; Devan, K; Nashine, B.K; Padma Kumar, G; Suresh Kumar, K.V; Varatharajan, S; Mohanakrishnan, P; Srinivasan, G; Bhaduri, Arun Kumar (23 December 2016). "Development of fast breeder reactor technology in India". Progress in Nuclear Energy. 101 (101): 19–42. doi:10.1016/j.pnucene.2017.03.015.
  4. ^ Puthiyavinayagam, P; Devan, K; Aithal, SR (2017). "Advanced Design Features of MOX Fuelled Future Indian SFRs" (PDF). International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17) Programme and Papers. IAEA-CN245-300: v – via International Atomic Energy Agency.
  5. ^ "BARC Highlights,Reactor Technology & Engineering" (PDF). Bhabha Atomic Research Centre. Retrieved 21 March 2021.
  6. ^ Choudhry, Nakul; Riyas, A (February 2013). "3D core burnup studies in 500 MWe Indian prototype fast breeder reactor to attain enhanced core burnup". Nuclear Engineering and Design. 255: 359–367. doi:10.1016/j.nucengdes.2012.11.011.
  7. ^ Devan, K (2008). "A new physics design of control safety rods for prototype fast breeder reactor". Annals of Nuclear Energy. 35 (8): 1484–1491. doi:10.1016/j.anucene.2008.01.013.
  8. ^ Lee, S.M; Govindarajan, S; Indira, R (1996). "Conceptual design of PFBR core" (PDF). IAEA-Tecdoc. International Atomic Energy Agency. 907.
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