IPHWR-700
About
The IPHWR-700 is a PHWR designed by BARC that operates at 700 MWe and about 250 degrees Celsius. It is designed for large-scale electricity but could be adapted for desalination or district heating.
| Developer | Bhabha Atomic Research Centre (BARC) |
|---|---|
| Country of Origin | India |
| Size | Large |
| Type | Pressurized Heavy Water Reactor (PHWR) |
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Analysis
4
Deployment Timescale
Score Justification
Multiple IPHWR-700 units are operational, and the broader IPHWR design family has accumulated substantial construction and operating experience. The design relies on conventional, site-built construction methods and a high proportion of long-lead specialized components, which contribute to longer construction timelines.
By indicator
- 4/4 Regulatory Engagement
To what extent has the reactor developer engaged with a recognized nuclear regulatory authority in the licensing process? (30% of total score) - 6/6 Technology Precedent
Has the reactor design, or a sufficiently similar design, been certified anywhere in the world? (10% of total score) - 1/3 Modularity
What share of total reactor systems can be manufactured off-site in controlled factory environments rather than constructed on-site? (15% of total score) - 1/4 Specialization
To what extent do construction activities and components require lengthy qualification processes? (15% of total score) - 5/5 Supply Chain
How mature and available are suppliers for key reactor components and fuel services? (30% of total score)
1
Overnight Cost
Score Justification
Overnight costs for the IPHWR-700 are relatively high because of the large unit size, limited modularization, and the specialized components required for heavy water operation. These factors increase on-site construction scope and contribute to higher equipment and installation costs.
By indicator
- 1/4 Component Cost
What is the expected cost of the reactor’s major components? (40% of total score) - 1/6 Construction Cost
To what extent does the design reduce construction cost and risk through modular fabrication and limited nuclear-grade specialization? (60% of total score)
2
Operational Cost
Score Justification
Operational costs for the IPHWR-700 include relatively high maintenance and consumables expenses associated with heavy water inventory management, as well as higher decommissioning costs typical of large reactor units. Those costs are partially offset by the reactor’s natural uranium fuel, which has low front-end costs.
By indicator
- 3/3 Fuel Cost
What is the estimated cost of nuclear fuel per unit of electricity generated, including enrichment, fabrication, and back-end costs? (15% of total score) - 1/4 Maintenance Cost
What is the expected annual maintenance cost for the reactor and balance of plant systems, including consumables? (25% of total score) - 1/5 Staffing Level
How many full-time personnel are required to safely operate and maintain the reactor unit? (40% of total score) - 3/5 Spent Fuel & Radioactive Waste Management Cost
What are the expected operational costs associated with managing spent fuel, including interim storage, transport, disposal, or recycling? (10% of total score) - 1/5 Decommissioning Cost
What are the total lifetime contributions required for decommissioning, regardless of funding mechanism? (10% of total score)
3
Cost Predictability
Score Justification
The IPHWR-700 benefits from learning effects associated with a multiunit deployment history and a standardized design lineage. The scale and complexity of on-site construction can introduce schedule and cost variability.
By indicator
- 4/5 Prototype
To what extent has the reactor design been built, demonstrated, or commercially deployed in practice? (75% of total score) - 1/3 Modularity
What share of total reactor systems can be manufactured off-site in controlled factory environments rather than constructed on-site? (25% of total score)
4
Security
Score Justification
The IPHWR-700 uses natural uranium fuel, which eliminates the need for enrichment. However, the combination of natural uranium, efficient heavy water moderator, and low burnup rate of the IPHWR-700 can produce weapons-usable plutonium, if irradiated on a very short time scale. BARC built in security by design by creating multitier physical barriers with intrusion detection systems within isolation zones.
By indicator
- 3/3 Fuel
What is the enrichment level and composition of the reactor fuel? (40% of total score) - 3/4 Nuclear Material Production
What is the potential for the reactor to produce weapons-usable nuclear material? (40% of total score) - 1/1 Security by Design
Has the reactor developer built in security by design? (20% of total score)
4
Safety
Score Justification
The IPHWR-700 is a high-pressure reactor design with redundant containment systems and an approved safety case. While it does not employ fuel with inherent accident-tolerant characteristics, the reactor benefits from well-understood safety features, including negative reactivity feedback mechanisms. It also incorporates an independent shutdown system using liquid neutron absorber injection, which rapidly terminates the chain reaction by flooding the moderator with a neutron-absorbing solution.
By indicator
- 2/2 Safety Case
How mature and publicly established is the reactor’s safety case with the regulator? (40% of total score) - 1/2 Shutdown Mechanism
How diverse, independent, and passive are the reactor’s shutdown systems? (20% of total score) - 0/1 Fuel With Safety Characteristics
Does the reactor use fuel with accident tolerance or inherent safety characteristics? (10% of total score) - 3/4 Pressure & Containment
How well does the reactor’s containment strategy protect from the release of radioactive material? (10% of total score) - 2/3 Passive Heat Removal
How long can the reactor remove core heat without operator intervention? (10% of total score) - 3/4 Coolant Reactivity
How chemically reactive is the reactor coolant? (10% of total score)
3
Spent Fuel & Radioactive Waste Management
Score Justification
The IPHWR-700 uses natural-uranium CANDU fuel, a well-characterized waste form assessed as technically acceptable for Canada’s Adaptive Phased Management approach. Waste streams include spent fuel, activated structural materials, gaseous waste, heavy water, and light water. On-site storage requirements are substantial, reflecting established CANDU practice with large dry storage facilities. While spent fuel volume per unit of energy is high, the reactor’s low burnup results in comparatively low decay heat at long cooling times.
By indicator
- 1/1 Spent Fuel Licensing Precedent
Has the spent fuel form been previously licensed for disposal? (20% of total score) - 2/4 Waste Streams
How many distinct waste streams require separate conditioning or handling pathways? (20% of total score) - 1/3 On-Site Storage
How much on-site area is required for interim spent fuel storage? (10% of total score) - 1/3 Spent Fuel Volume
What volume of spent fuel is produced per unit of electricity generated? (15% of total score) - 2/2 Decay Heat
What is the decay heat output of spent fuel at the 50-year interim storage milestone? (20% of total score) - 2/2 Time to Interim Storage
What is the average time until spent fuel can be transferred to interim storage? (15% of total score)
5
Supply Chain
Score Justification
The supply chain for the IPHWR-700 is well established because of the decades of HWR operation.
By indicator
- 2/2 Key Component Availability
To what extent are commercial or pilot-scale suppliers available for the reactor’s major components? (60% of total score) - 4/4 Fuel Availability
Are suppliers available for both fuel fabrication and enrichment required by the reactor design? (40% of total score)