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Sustainable Energy Security from Fast Breeder Reactors. P. Puthiya Vinayagam and P. Chellapandi Indira Gandhi Centre for Atomic Research Kalpakkam, India. 6 th Nuclear Energy Conclave Organised by India Energy Forum at New Delhi on 14 th October 2014. - PowerPoint PPT Presentation
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P. Puthiya Vinayagam and P. ChellapandiIndira Gandhi Centre for Atomic Research
Kalpakkam, India
Sustainable Energy Security from
Fast Breeder Reactors
6th Nuclear Energy ConclaveOrganised by India Energy Forum at New Delhi on 14th October 2014
Provides a perfect link covering the natural nuclear resources of India
Effective utilisation of uranium – better resource management
Long term energy supply
Higher growth rate with breeding
Waste management - Incineration of radioactive waste from spent fuel and reduction of long term storage requirements
Enhanced performance parameters – high temp of operation leading to higher thermodynamic efficiency
Closed fuel cycle program is essential in the 2nd and 3rd stage
FBR : A Vital Stage in Indian Nuclear Power Program
FBRs : Inevitable for long term security & sustainability of nuclear power
Nat U
Pu & Depleted U
U233
Th
Stage I
Stage II
Stage III
Pu
U233
Th
Growth and Waste Minimization Strategy
Growth
Higher growth rate possible only if fuel generation is more;
Hence, breeders are essential (with high breeding ratio)
Recycling & Waste Minimization
Effective incineration with higher energy spectrum;
FBRs are high energy systems
Key Parameters: Burnup, Breeding Ratio & Doubling Time (Growth)
FBR Program in India
• FBR program started with construction of test reactor –
Fast Breeder Test Reactor with French know-how
• Prototype scale reactor : PFBR 500 MWe - Indigenous
Design & Construction – Under commissioning
• Comprehensiveness in development of Design based on
systematic R&D
• Synthesis of Operating Experiences
• National & International Collaborations
• Emphasis on sustaining quality human resources
• Future FBR Design : Improved economy & enhanced
safety
Fast Breeder Test Reactor
FBTR, in operation since 1985, is the flag-ship of IGCAR and is the test bed for fast reactor fuels and materials.
22 campaigns were completed so far for various irradiation programs.
Training of PFBR operators in progress
High burnup experience from mixed carbide fuel (165 GWd/t) PFBR MOX fuel tested and design demonstrated (112 GWd/t) Structural materials irradiation program Irradiation testing of advanced fuel types (vibrocompacted MOX fuel) Sodium systems performance is excellent and confidence in operation Material and fuel irradiation for other Indian reactors which are under
development
Major Achievements
40 MWt
13.5 MWe
Loop type
(Pu-U)C fuel
MFBR1000 MWe
Proven Prototype Concepts
Design, Mfg. and Safety re
view Experience
FBR 1 & 2 - 500 MWeMOX, Pool, Twin
units, Indigeneous
PFBR - 500 MWeMOX , Pool type, Indigeneous
Metal fuel Demonstration Fast Reactor – 500 MWeSame reactor concepts,
Indigeneous
Evolution of SFR Power Reactor Concepts
FBR-600 MWe Preliminary Conceptual Design options worked outPower : 600 MWe with expanded coreTargets : Higher breeding ratio compared to PFBRVessel size : same as PFBR Reactor Assembly design concepts : same as FBR1&2Core type: Heterogeneous as an optionAdvantage : Existing MOX technology & economy
Improved economy- Higher reactor power (600 MWe – Specific capital cost reduction) - Core optimisation for higher breeding ratio (not fuel inventory alone)- Specific material inventory reduction (t/MWe) (~ 20% in 316LN & carbon steel, ~ 15% in Ferritic steel, ~ 6% in sodium)- Simplified systems and components (e.g fuel handling)- Integrated manufacture & erection - reduction of gestation period
-Twin units sharing non-safety systems (cost reduction)-Steam generator (longer length ) & Standardized turbine
Enhanced safety - Addition of passive features in shutdown systems & addition of 3rd system based on liquid absorbers / B4C granules
- Enhanced reliability of decay heat removal systems with addition of passive features- Enhanced in-service inspection and repair features
Design Approach for Future FBRs
No major R&D requirement for Design as well as Technology development beyond those planned for 500 MWe reactors
FBR-600 MWe : Plant Parameters
Parameter PFBR FBR-600
Power, MWe 500 600
Fuel MOX MOX
Reactor coolant inlet/outlet temp, oC 397 / 547 397 / 557
Core layout Homogeneous Heterogeneous
No. of enrichment zones 2 1
Fissile enrichment, % 20.7 / 27.7 29.5
Fissile inventory, kg 1980 3310
Breeding ratio 1.05 1.13
Secondary loops 2 2
No. of Primary Sodium Pump 2 3
No. of IHX 4 4
No. of Secondary Sodium Pump 2 2
No. of SG / loop (tube height, m) 4 (23 m) 3 (30 m)
Steam temp/Pressure (oC / MPa) 490 / 17 510 / 17
Main vessel diameter, m 12.9 12.9
Load factor, % 75 85
Strategy for the Development of Metal Fuel Reactors
Pin and subassembly level irradiation in FBTR mainly to demonstrate pin production, reprocessing and re-fabrication technologies
Irradiation of a few subassemblies in PFBR after demonstrating the stable operation at rated power levels
Re-fabrication of pins for both FBTR & PFBR irradiation pins in an integrated facility
Accumulating operating experiences through demonstration plant Metal Demonstration Fast Reactor (MDFR), preferably of medium size plant with reasonable breeding
Deriving technological maturity on pyro metallurgical recycle technology in industrial scale
Demonstration of closed fuel cycle mode through MDFR
Series construction of 500-1000 MWe plants
Metallic Fuel Development
Doubling time: 30years for oxide, 12 years for metal (ternary fuel) and 8 years for improved metallic fuel (binary fuel without Zr)
Reference compositions:
U-19%Pu-6%Zr (sodium bonded)U-15% Pu (mechanically bonded)
Sodium bonded EU-6%Zr and U-Pu-Zr pins fabricated and are under irradiation in FBTR
Physicochemical property measurements and clad compatibility studies under way
Scenario for Metal Fuel Power Reactor Assessment with optimum pin diameter 8 – 8.5 mm for growth
Based on preliminary assessments with a matrix of case studies
ParameterSodium Bond Mech Bond
10 % Zr 6 %Zr 0 % ZrLHR, W/cm 450-530 420-470 375-400
Breeding Ratio (including ext. blanket )
1.2 – 1.25 1.30 – 1.35 1.4 – 1.45
Burnup, GWd/t 100-125 100-125 100-125Sodium Void Reactivity coeff, $ 4.5 – 5.0 5.0 – 5.5 5.5 – 6.0
Fissile enrichment zones (500/1000) 2 / 3 2 / 3 2 / 3
No of SA (500 MWe) 180 195 220
Na outlet temp oC 510-520 510-520 510-520
Spent fuel storage Sodium Sodium Water
Reprocessing Pyro Pyro Purex
Plant Parameters : A Comparison (MOX & Metal)
Closed Fuel Cycle for PFBR
• Closure of fuel cycle of PFBR is essential to make it self-sustaining
• Thermal reactor Plutonium will be used for building of more FBRs.
• Fast Reactor Fuel Cycle Facility (FRFCF) being located at Kalpakkam.
• FRFCF would be a ‘first of its kind’ facility in the country
• Co-location of the facility with reactor would reduce cost due to transport and also avoid security issues
• Basic technologies required for the facility is available
• Designed to augment additional capacity to meet the requirements of two more 500 MWe FBRs to be built at Kalpakkam site.
FRFCF – Bird’s Eye View
MA Burner – design to burn self-production and external MA feed;
MA Burnt ~ 100 kg/GWey MA produced ~ 20 kg/GWey Net Transmutation ~80kg/GWey
Sustainability Consideration
Minor Actinide Management – A scenario
• Study based on Indian power reactor program
• Metal fast reactors are ideal for MA burning
• Introduction of MA Burner together with power production at an appropriate time
• Fast Breeder Reactors – Essential for Energy Security and Sustainability
• Experience from FBTR operation and PFBR design, manufacture, construction & safety review have given confidence for FBR deployment in series in closed fuel cycle mode. No technological constraints are foreseen.
• Towards higher growth rate, R&D on metal fuel with high breeding potential along with associated fuel cycle technologies is in progress.
Summary
Thank You for your attention