Prototype Fast Breeder Reactor (PFBR) at Kalpakkam Achieves Criticality: India’s Nuclear Milestone

India has marked a major milestone in its nuclear energy programme as the indigenously designed and built Prototype Fast Breeder Reactor (PFBR) at Kalpakkam in Tamil Nadu attained criticality.More on News:

• It is fully designed by BHAVINI and Indira Gandhi Centre for Atomic Research (IGCAR).
  • BHAVINI (Bharatiya Nabhikiya Vidyut Nigam Limited) is a PSU under the Department of Atomic Energy responsible for building and operating fast breeder reactors in India.

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About Prototype Fast Breeder Reactor

• The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe nuclear reactor that uses fast neutrons for sustaining the nuclear chain reaction without the need for a moderator.
  • Unlike Pressurised Heavy Water Reactors (PHWRs) that use heavy water to slow neutrons, PFBR directly uses fast neutrons to sustain the chain reaction, improving fuel efficiency.
• Breeder Reactor: It is designed as a breeder reactor, meaning it produces more fissile fuel (Plutonium-239) than it consumes, thereby enhancing fuel efficiency and sustainability.
• • The reactor converts fertile isotopes into fissile fuel through neutron absorption:
    • Uranium-238 → Plutonium-239 (in the core)
    • Thorium-232 → Uranium-233 (in the blanket region)
• Fuel: Mixed Oxide (MOX) fuel, consisting of a uranium–plutonium blend, derived from reprocessed spent fuel of Pressurised Heavy Water Reactors (PHWRs).
• Coolant: Liquid sodium (over 1,750 tonnes) used as a coolant, ensuring high heat transfer efficiency while maintaining a fast neutron spectrum due to the absence of moderation.
• Closed Fuel Cycle: Involves reprocessing and recycling of spent nuclear fuel to recover usable fissile materials, thereby minimising radioactive waste and maximising resource efficiency.

Challenges

• High Cost: The PFBR involves high capital costs in terms of construction and requires significant expenditure on maintenance, making it economically demanding.
• Sodium Coolant Risks: The use of liquid sodium as a coolant poses risks as it is highly reactive, especially when it comes into contact with air or water, raising safety concerns.
• Safety and Design Complexity: The reactor has a complex design and operational mechanism, which increases safety challenges and demands advanced technological expertise.
• Long Gestation Period: The development and deployment of PFBRs involve a long gestation period, delaying returns on investment and large-scale implementation.
• Limited Global Experience: Only a few countries have successfully operated fast breeder reactors, limiting availability of proven models and expertise.
  • Past challenges faced by countries like France and Japan in their breeder reactor programmes highlight operational difficulties.

Significance

• Strategic Importance: The PFBR advances the second stage of India’s three-stage nuclear programme, strengthening the country’s long-term nuclear roadmap.
  • It brings India closer to the utilisation of its vast thorium reserves in the third stage
• Energy Security: It helps reduce dependence on imported uranium by efficiently using available nuclear fuel.
  • Ensures a sustainable and closed nuclear fuel cycle for long-term energy needs.
• Aligned with Aatmanirbhar Bharat initiative: The project has been built indigenously with contributions from over 200 Indian industries, including several MSMEs, aligning with the government’s push for self-reliance under the Aatmanirbhar Bharat initiative.
• Clean Energy Transition: It supports low-carbon electricity generation, contributing to cleaner energy production.
  • Aligns with India’s climate commitments and sustainable development goals.
• Technological Achievement: India becomes the second country after Russia to develop a commercial fast breeder reactor.
  • It demonstrates strong indigenous capabilities in advanced nuclear reactor technology and engineering.

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About India’s 3 Stage Nuclear Programme

• First Stage: PHWRs (Pressurised Heavy Water Reactors)
  • Fuel Use: Natural uranium (U-238) is used as fuel.

• • Moderator & Coolant: Heavy water (D₂O) is used as both moderator and coolant.
  • Output: Produces Plutonium-239 (Pu-239) in spent fuel.
  • Status: This stage is fully operational and forms the backbone of India’s nuclear power programme.
• Second Stage: Fast Breeder Reactors (FBRs)
  • Key Feature: Designed to produce more fuel than they consume (breeding capability).
  • Fuel Type: Uses Mixed Oxide (MOX) fuel (uranium + plutonium).
  • Mechanism: Converts U-238 into Pu-239 through nuclear transmutation.
  • Energy Efficiency: Enhances energy extraction from uranium by ~60 times.
  • Strategic Role: Builds plutonium inventory required for the third stage.
• Third Stage: Thorium-Based Reactors
  • Fuel Cycle: Converts Thorium-232 into Uranium-233 (fissile material).
  • Objective: To utilise India’s vast thorium reserves available in coastal sands of states like Kerala, Tamil Nadu, Odisha, Andhra Pradesh, etc.
  • Future Technology: Involves advanced systems such as Molten Salt Reactors (MSRs) (under development).

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