Back End Fuel Cycle: Indian Scenario
Madhuri Shetty Nuclear Recycle Group Bhabha Atomic Research Centre, Mumbai
Technical Meeting on
Integrated Approaches to the Back End of the Fuel Cycle
Vienna, 17 – 19 July 2018
Back End Fuel Cycle: Indian Scenario Madhuri Shetty Nuclear Recycle - - PowerPoint PPT Presentation
Back End Fuel Cycle: Indian Scenario Madhuri Shetty Nuclear Recycle Group Bhabha Atomic Research Centre, Mumbai Technical Meeting on Integrated Approaches to the Back End of the Fuel Cycle Vienna, 17 19 July 2018 Outline India s
Technical Meeting on
Vienna, 17 – 19 July 2018
was designed by
into rector system helps in exploiting the full potential of nuclear power and maximize the resource utilization
generation as it can increase the quantum of energy derived from Uranium
programme
The goal of three stage Indian nuclear power programme is long term resource sustainability
www.indiaatcop22.org
Advanced Heavy Water Reactor (AHWR) Fast Breeder Reactor 540 MW Pressurized Heavy Water reactor (PHWR)
Fuel Fissile + Fertile Fissile partly spent Fertile partly converted Spent Fuel cooling & final disposal in Geological Repository
Huge energy potential !! Nuclear Reactor
Fuel Fissile + Fertile Fissile partly spent Fertile partly converted Reprocessing Fertile + Fissile HLW to Interim storage and finally to Deep Repository Fuel Fabrication Huge energy potential !! Nuclear Reactor
▪ With reprocessing and recycle energy potential is enhanced several ten folds and even our limited uranium resources represent an energy source larger than coal ▪ Near elimination of fissile material from waste. ▪ Reprocessing and recycle also enables use of Thorium which is abundant in India ▪ Thorium advantages : high burn up, reduced minor actinides production, higher safety margins, higher proliferation resistance etc. ▪ India has a unique opportunity here as eventually Thorium would assume importance worldwide ▪ Closed fuel cycle and reprocessing also help in reducing the nuclear waste burden and radio-toxicity of finally disposed HLW.
Spent fuel from nuclear reactor fuel storage pond Reprocessing of spent fuel HLLW treatment U & Pu product for recycle /reuse Hull waste disposal Recovery of Cs137, Sr90, Ru106 etc for societal benefits P&T of MAs in FBR / ADS HLW to Interim storage and finally to Deep Repository ILLW treatment and disposal
Recovery
useful fission products and minor actinides before waste immobilization. ▪ Successful demonstration of actinides partitioning from HLW done at plant scale. ▪ Recoveries better than 99.9 % has been demonstrated
Immobilization of waste oxides in stable and inert solid matrices.
▪ Partitioning permits use of tailor made matrices for conditioning selected waste streams in parallel with the established vitreous matrices.
Interim retrievable storage of the conditioned waste under continuous cooling.
▪ High capacity melter for vitrification ▪ Advanced melters like cold crucible are being implemented for high burn up fuel. ▪ Studies for deep geological repositories in progress.
Volume of High Level Vitrified waste generated for power
consumption of an average family for entire life
Volume of waste if actinide is also separated from HLW
Radiotoxicity of spent fuel is dominated by : FPs for first 100 years. subsequently, Pu (>90%) After Pu removal Minor Actinides specially Am (~ 9%)
Natural decay of spent fuel radiotoxicity
With early introduction of fast reactors using (U+Pu+Am) based fuel, long term raditoxicity of nuclear waste will be reduced. 200,000 years 300 years
IRF Plant inputs Interim Storage Short Lived Waste Products For Disposal U & Pu MOX fuel
Cs 137, Sr90, Actinides
Vitrified Waste Canisters In Air Cooled Vault Compacted Hull Canisters In Shielded Vault Non Hull Alpha Waste Products In Shielded Cells
Spent Fuel Inactive Chemical
Gaseous /Liquid Discharge (As Low As Reasonably Achievable)
Long Term Storage
Fast Breeder Reactors
(Initial Phase)
Pu & RU PHWR Pu & RU Surplus Pu Fast Breeder Reactor Capacity Expansion Thorium
233U for Third Stage
Pu Fast Breeder Reactors
(Final Phase)
RU RU
Surplus Pu
– Codes, Standards, Manuals are available on Regulatory body Network sites – Technical information regarding various R&D activities available on closed network system Information Gateways / Data storage facilities – Periodic reports and information regarding annual meetings are available and preserved – Data and knowledge preservation in digital format – Classified documents preservation under access control in hard copies as well as digital format
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Initial Safety related documents DBR/PSAR Detailed Plant level Review Detailed safety Review following set guidelines Revision and approved copy in practice in routine practice Tech Specification & SOPs
Annual RIT Review Licensing & Relicensing Procedures Authorization/ Re- authorization of facilities on regular interval
from reprocessed fissile & fertile material for recycle.
recovery of important fission products
approach in the back end fuel cycle.