Back End Fuel Cycle: Indian Scenario Madhuri Shetty Nuclear Recycle - - PowerPoint PPT Presentation

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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


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SLIDE 1

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

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SLIDE 2

Outline

  • India’s Three stage Nuclear program
  • Fuel cycle options: Open fuel cycle and Closed fuel cycle
  • Strategies of spent management practices in India
  • Integrated Nuclear Recycle Plant: A new concept
  • Interfaces in back end cycle activities
  • Information & Knowledge management
  • Role of Regulatory body
  • Conclusion
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SLIDE 3

INDIAN NUCLEAR PROGRAM PRESENT SCENARIO

➢ At present 22 reactors are in operation ➢ Another 9 reactors are under construction while 10 have been approved and in process of siting ➢ There are various research reactors also which are operational ➢ Further planning to add more capacity in future to reach 63 GWe by 2050

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SLIDE 4

India’s Three Stage Nuclear Power Programme

  • India has limited Uranium resources and abundant Thorium resources
  • A Three Stage Nuclear Programme

was designed by

  • Dr. H. J. Bhabha for
  • ptimum utilization of limited uranium and abundant thorium .
  • Closing fuel cycle by reprocessing and recycling fissile & fertile material back

into rector system helps in exploiting the full potential of nuclear power and maximize the resource utilization

  • Success of closed cycle would depend on utilization of Plutonium for power

generation as it can increase the quantum of energy derived from Uranium

  • Reprocessing is a vital link between the stages of three stage nuclear energy

programme

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SLIDE 5

Indian Three stage Nuclear Power Program

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)

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SLIDE 6

Fuel cycle options

Fuel Fissile + Fertile Fissile partly spent Fertile partly converted Spent Fuel cooling & final disposal in Geological Repository

Open or Once Through Fuel Cycle

Huge energy potential !! Nuclear Reactor

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Fuel cycle options

Closed Fuel Cycle

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

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India’s strategy: Closed Fuel Cycle

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SLIDE 9

Features of closed fuel cycle

▪ 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.

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SLIDE 10

Steps in Back End Fuel cycle: Closed fuel cycle

  • Under water cooling of spent nuclear fuel in spent fuel pool at reactor site

to reduce decay heat and specific activity of spent fuel before taking up for reprocessing

  • Transportation of spent fuel from reactor site to reprocessing site
  • Reprocessing of spent nuclear fuel for recovery of fissile and fertile material
  • Fuel re-fabrication from the recovered fissile and fertile material
  • HLW management before final disposal into deep geological repositories

and management of solid, liquid and gaseous waste for final disposal

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SLIDE 11

Strategy of spent fuel management in India

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

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High Level Liquid Waste Treatment

 Recovery

  • f

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.

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SLIDE 13

▪ 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

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SLIDE 14

Adopting closed fuel cycle also reduces nuclear waste burden.

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

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India’s Five decades of experience in Reprocessing of PHWR Spent Fuel

  • Enormous

experience

  • f

50 years

  • f

PHWR spent fuel reprocessing

  • Product recoveries better than 99 %
  • Decontamination Factors of the order of 107
  • Environmental discharges are quite below the regulatory limits

Concept of Integrated Nuclear Recycle Plants

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SLIDE 16

Integrated Recycle Facility

  • Works on solid-in solid-out concept and includes reprocessing

facility, waste management facility and fuel fabrication facility

  • Designed for Thermal Reactor spent fuel management
  • Reprocessed Uranium and Plutonium from these plants will be

supplied for next generation reactors like FRs and Advanced Heavy Water Reactor

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SLIDE 17

Inputs & Outputs

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

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SLIDE 18

Benefits of Integrated management & responsibility for Back end fuel cycle activities

  • Standardization in all stages, from design to commissioning
  • Minimise duplication of systems/ equipment
  • Optimised man /material movement.
  • Reduced Capital and O&M Cost
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SLIDE 19

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

Strategies for U & Pu utilization

Surplus Pu

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India: Reprocessing of Thorium Based Fuel

  • Thoria based fuel: Third stage of Indian Nuclear Three Stage Program
  • A Pilot plant and an engineering demonstration facility for reprocessing of

Thoria based fuel

  • Successfully demonstrated processing of Thoria bundles irradiated in

PHWRs and utilization of U233 in R&D facilities.

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SLIDE 21

Interfaces between back end cycle activities

  • Reactor and spent fuel storage and Transportation :

– Extent of irradiation in nuclear reactor and decay heat of spent fuel at the time of discharge governs spent fuel storage/cooling time – Spent fuel storage capacity and design for decay heat removal – Requirement of Away From Reactor storage facilities – Consideration of safety requirements during design, construction and operation of transportation system like cask design for handling activity, decay heat and Physical Protection requirements during transportation etc

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Interfaces between back end cycle activities

  • Issues in Storage and Reprocessing :

– Storage period governs spent fuel specific activity – Economical effects due to spent fuel specific activity on back end activities e. g. shielding requirements, operating cost, waste generation etc. – Management of split pins/failed fuel

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Interfaces between back end cycle activities

  • Reprocessing steps and End use of product:

– End use of product governs the extent of product specifications – Minor actinides to be burnt in FBRs or ADSS, – Management of additional radioactive waste like spent organic, resins and other alpha waste

  • Partitioning & Transmutation and waste management:

– Recovery of fission products like Cs137, Sr90, Ru106 for societal benefits – Reduced heat load and Radio-toxicity of waste by separation of actinides – Use of actinides as fuel in FRs or ADSS as fuel

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Information management & Knowledge management

– 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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SLIDE 25

– Framing of regulatory guidelines as well as ensuring safety of public and environment during design, construction, commissioning,

  • peration and decommissioning of the facility.

– Ensuring proper knowledge management that includes new knowledge creation as well as knowledge sharing, storage and refinement.

Role of regulatory body

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REGULATORY ASPECTS

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

O&M FACILITIES SAFETY

Annual RIT Review Licensing & Relicensing Procedures Authorization/ Re- authorization of facilities on regular interval

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Conclusion

  • In closed fuel cycle, a significant fraction of the energy input would come

from reprocessed fissile & fertile material for recycle.

  • Fuel cycle with reprocessing and P&T options for recycling of actinides,

recovery of important fission products

  • Steps towards Information management and Knowledge management
  • Integrated Nuclear Recycle Plant is one step taken for the integrated

approach in the back end fuel cycle.

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SLIDE 28