indian strategy for management of spent fuel from nuclear power reactors s.basu, india
TRANSCRIPT
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Indian strategy for management of spent
fuel from Nuclear Power Reactors
S.Basu, India
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Energy scenario in India
• At the present growth rate, Indian economy will double every eight years
• Growing population
• Reaching well above per capita world average consumption
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• Nuclear energy is to meet 25% to 50% of the total energy requirement
• Nuclear capacity will reach 20 Gwe and more by 2020
• 200 Gwe and above generation capacity is targeted by the middle of the century
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• Large nuclear energy requirement
• Limited Uranium resources
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Spent Fuel is a resource for India
• All spent fuel will be reprocessed• Storage of spent fuel is an interim
activity
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Indian three stage programme envisages
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I Stage : Pressurized Heavy water reactor with Natural Uranium fuel
Interim storage in spent fuel storage pools and subsequent reprocessing
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II Stage : U-Pu based Fast Breeder Reactors
based on MOX/metallic fuel
Interim storage of spent fuel in reactor/water pool & Reprocessing in fast reactor fuel cycle facilities.
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III Stage: Th-Pu and Th-U233 (MOX) based reactors
Interim storage of above fuel and subsequent reprocessing of
Th-Pu-U233 or Th-U233 fuel
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• Reprocessing of short cooled fuel
• Aqueous reprocessing of oxide fuel
• Aqueous/Pyro chemical reprocessing for metallic fuel
Fast reactor fuel reprocessing
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Fast reactor spent fuel storage
• Initial cooling in reactor
• Sodium removal
• Interim Storage in water pools
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Thorium fuel reprocessing
• Three component reprocessing, Th – Pu –U233
• Two component reprocessing, Th – U233
• U232 related issues
• Thorium storage
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Recent nuclear agreements opened up possibility for
LWRs of various types based on enriched UraniumInterim storage and subsequent reprocessing of oxide spent fuel ( High burnup fuel)
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Pressurized Heavy Water Fuel using Recycled Uranium (oxide)
Uranium in spent fuel of LWRs is slightly enriched. Suitable for use in PHWRs.
Interim storage and Reprocessing of Recycled Uranium based Spent Fuel
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Other impact of nuclear agreement is availability of Natural Uranium from foreign sources
PHWRs based on natural Uranium obtained from foreign sources Interim storage and reprocessing of spent fuel
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Spent fuel storage pool
• Intermediate storage • Adequate cooling period• Water cooled• Buffer for the period between discharge from
reactor and reprocessing
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Storage period for spent fuel
• Longer storage of spent fuel simplifies the reprocessing and waste management systems
• Shorter storage period results in earlier availability of Pu for power generation
• Early reprocessing would require storage of high level waste for longer period before vitrification
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Reprocessing requirements
• Natural Uranium (Indian) - PHWR• Natural Uranium (Foreign) - PHWR• Enriched Uranium- LWRs of four types• Recycled Uranium(LWR fuel repro.) - PHWR• Fast reactor MOX fuel • Fast reactor metallic fuel• Th – Pu – U233 fuel• Th – U233 fuel
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Waste management
High level waste is vitrified and stored in interim storage facilityCesium and Strontium recovery is planned
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Spent fuel Transportation
All transportation will be through land routes using transfer casks and trailers meeting all regulatory requirementsFor Coastal sites Reprocessing facilities are co-located with power reactors . This will minimize fuel transportation in public domain
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Larger size Integrated Nuclear Recycle Plant
* So far smaller size reprocessing plants were co-located with waste management and fuel fabrication facilities
* Future plants will be based on integrated facility for reprocessing and waste management. Fuel fabrication facility will also be integrated in most cases
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Challenges : construction and operation of larger size plants
• Extension of available technology; for low and high burn up fuel
• Use of newer equipment
• Cost reduction
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Reprocessing and fabrication of metallic fuel
• Pyro – chemical technique for reprocessing• Electro reduction technique for conversion
from oxide to metal• Metallic fuel fabrication• Commercial scale operation
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Present activities in the back end
• Operation of small size plants• Construction and commissioning of two more
reprocessing plants and associated facilities (augmentation activities)
• Design and construction two large size integrated plants, one for PHWR and the other for fast reactor spent fuel
• Plant designs aim at significant reduction in discharges & improvement in safety & security
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Safety Guides
• Comprehensive safety codes and guides are required for the back end of fuel cycle
• Should cover reprocessing ,waste management and repository
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Conclusion
• Uranium Resource constraint ; Countries aiming large and sustained nuclear generation has to opt for closed fuel cycle
• Waste volume; Significant reduction in waste volume is possible only through closed fuel cycle route
• Indian nuclear recycle programme is poised for major expansion, matching the enhanced power generation plans