VVER-1200
About
The VVER-1200 is a Gen III+ PWR producing roughly 1,200 MWe. It is developed for large-scale electricity generation, but it can be adapted for cogeneration, especially district heating and cooling and desalination.
| Developer | Rosatom |
|---|---|
| Country of Origin | Russia |
| Size | Large |
| Type | Pressurized Water Reactor (PWR) |
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Analysis
4
Deployment Timescale
Score Justification
The VVER-1200 is regulator-approved and operational in Eastern Europe. The design relies on a large, site-built construction model, with extensive nuclear-grade structures and safety systems assembled on–site, limiting the degree of modularity. The supply chain is mature, with established manufacturing of VVER-class components and standard PWR fuel services.
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) - 2/4 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
Owing to its GW-scale, the VVER-1200 has high overnight capital costs driven by large containment structures, extensive safety-related systems, and a substantial scope of nuclear-grade installation work. The nuclear island includes large forgings, steam generators, reactor coolant pumps, and safety-class instrumentation and control, combined with significant site civil works and quality assurance requirements.
By indicator
- 1/4 Component Cost
What is the expected cost of the reactor’s major components? (40% of total score) - 2/6 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
The large reactor footprint and extensive support systems of the VVER-1200 drive higher staffing, maintenance, and decommissioning requirements. Fuel costs remain low due to the use of standard–assay LEU fuel. Waste management is midrange, consistent with routine PWR operational waste streams and spent fuel handling.
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)
4
Cost Predictability
Score Justification
Cost Predictability for the VVER-1200 benefits from a mature, regulator-reviewed design with multiple deployed units, which provide substantial construction and operating experience. The reliance on large, site-built nuclear structures and limited factory modularization means that costs remain sensitive to site conditions, labor productivity, and construction management performance.
By indicator
- 5/5 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)
5
Security
Score Justification
The VVER-1200 uses LEU fuel, and its thermal spectrum is not optimized to produce weapons-usable nuclear material. Rosatom has incorporated security by design, especially in terms of physical security. The physical security system includes engineered alarms and controls.
By indicator
- 3/3 Fuel
What is the enrichment level and composition of the reactor fuel? (40% of total score) - 4/4 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 VVER-1200 has a regulator-approved safety case. In addition to the standard of negative reactivity feedback, the VVER-1200 uses an independent active shutdown system in the form of control rods. It also employs a passive heat removal system that uses the steam generator as the heat exchanger, enabling up to 72 hours of passive core heat removal through a natural circulation loop.
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 VVER-1200 uses standard-assay LEU UO₂ fuel, which has been licensed and qualified for disposal in multiple countries. This familiar spent fuel form can usually be transferred to interim storage within five years. The reactor does not introduce novel waste streams that require separate treatment and handling beyond past practice.
By indicator
- 1/1 Spent Fuel Licensing Precedent
Has the spent fuel form been previously licensed for disposal? (20% of total score) - 3/4 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) - 2/3 Spent Fuel Volume
What volume of spent fuel is produced per unit of electricity generated? (15% of total score) - 1/2 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 VVER-1200’s Supply Chain score reflects established manufacturing pathways for large PWR nuclear island components and conventional balance of plant equipment. There is a robust, commercial supply for standard-assay LEU enrichment and LWR fuel fabrication services.
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)