Pressurised Heavy Water Reactors
Kartavya Desk Staff
Source: BS
Context: The Atomic Energy Regulatory Board (AERB) has granted operational licences to NPCIL for two indigenous 700 MWe Pressurised Heavy Water Reactors (PHWRs) at Kakrapar Atomic Power Station (Units 3 & 4) in Gujarat.
About Pressurised Heavy Water Reactors:
• What is a PHWR?
• A nuclear fission reactor that uses natural uranium as fuel and heavy water (D₂O) as both coolant and neutron moderator. Designed to operate with online refuelling, allowing continuous energy production.
• A nuclear fission reactor that uses natural uranium as fuel and heavy water (D₂O) as both coolant and neutron moderator.
• Designed to operate with online refuelling, allowing continuous energy production.
• Developed By:
• Initially with Canadian support (Rajasthan-1), later fully indigenised by BARC (Bhabha Atomic Research Centre) and NPCIL (Nuclear Power Corporation of India Ltd) under the Department of Atomic Energy.
• Initially with Canadian support (Rajasthan-1), later fully indigenised by BARC (Bhabha Atomic Research Centre) and NPCIL (Nuclear Power Corporation of India Ltd) under the Department of Atomic Energy.
• Historical Evolution:
• RAPS-1 (1973): With Canadian collaboration. RAPS-2 onwards: Entirely developed by Indian scientists post-AECL withdrawal. Progression from 220 MWe → 540 MWe → 700 MWe with full domestic R&D and manufacturing.
• RAPS-1 (1973): With Canadian collaboration.
• RAPS-2 onwards: Entirely developed by Indian scientists post-AECL withdrawal.
• Progression from 220 MWe → 540 MWe → 700 MWe with full domestic R&D and manufacturing.
• How Does It Work?
• Uses heavy water as moderator to slow down neutrons and maintain a sustained chain reaction. Fuel rods (natural uranium) are inserted into pressure tubes within a calandria vessel. Hot pressurised heavy water carries heat to steam generators → drives turbines → generates electricity. Control rods and ECCS systems regulate power output and enhance safety.
• Uses heavy water as moderator to slow down neutrons and maintain a sustained chain reaction.
• Fuel rods (natural uranium) are inserted into pressure tubes within a calandria vessel.
• Hot pressurised heavy water carries heat to steam generators → drives turbines → generates electricity.
• Control rods and ECCS systems regulate power output and enhance safety.
• Key Features of 700 MWe PHWRs:
• Fully indigenous design and operation, including construction, fuel fabrication, and control systems. Online refuelling system improves efficiency and reduces downtime. Equipped with twin fast-acting shutdown systems, double containment, and passive heat removal. Digital Instrumentation and Control Systems enhance real-time safety and automation. On-site heavy water moderation and cooling reduces external dependency and enriches neutron economy.
• Fully indigenous design and operation, including construction, fuel fabrication, and control systems.
• Online refuelling system improves efficiency and reduces downtime.
• Equipped with twin fast-acting shutdown systems, double containment, and passive heat removal.
• Digital Instrumentation and Control Systems enhance real-time safety and automation.
• On-site heavy water moderation and cooling reduces external dependency and enriches neutron economy.
• Significance of Recent Licence:
• Boosts India’s 10-reactor PHWR fleet mode rollout, part of its strategy to add 7000 MWe capacity indigenously. Confirms that India has mastered end-to-end nuclear tech from design to decommissioning.
• Boosts India’s 10-reactor PHWR fleet mode rollout, part of its strategy to add 7000 MWe capacity indigenously.
• Confirms that India has mastered end-to-end nuclear tech from design to decommissioning.