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MRIA SMPWR

Small Modular Pressurized Water Reactor

A conceptual Small Modular Nuclear Steam Supply System (NSSS) based on proven PWR/VVER principles. Designed for the Ukrainian energy model with primary focus on thermal energy production and flexibly controllable electricity generation.

~500 MWt
Thermal Power
75-90 MWe
Electrical Output
100 yrs
Design Life
24-36 mo
Fuel Cycle
MRIA SMPWR Protected Module with Air Defense
Protected Infrastructure

Wartime & Post-War Security

Given the realities of wartime and post-war conditions, MRIA SMPWR includes a multi-layer physical protection system — including radar detection, UAV countermeasures, and access control systems.

The Nuclear Island is designed for underground placement, using specialized high-strength concrete with ballistic and blast resistance to drastically reduce vulnerability to aerial attacks, artillery, and other external threats.

Modular Architecture

Scalable Multi-Module Configuration

The modular design enables flexible scaling from a single unit to multi-module complexes. Each module operates independently while sharing common infrastructure — turbine hall, cooling systems, and control facilities.

This approach allows for phased deployment, matching capacity to growing demand without over-investment. A typical multi-module complex can reach 300-500 MWe total electrical output.

MRIA SMPWR Multi-Module Configuration

Purpose & Vision

Primary Focus: Thermal Energy

Unlike conventional SMRs focused on electricity, MRIA SMPWR is optimized for district heating and industrial heat supply. Electricity generation is an integral but flexibly controllable secondary function.

Heat-first design philosophy

Evolutionary Approach

Based on proven VVER technology with decades of operational experience. No experimental or unproven technologies — focus on simplified licensing and industrial implementability.

  • Compatible with existing regulatory frameworks
  • Leverages existing expertise and supply chains

Technical Specifications

Nominal Thermal Power

~500 MWt

Electrical Output (gross)

75-90 MWe

Design Service Life

Up to 100 years

Design Pressure

~15.7 MPa

Coolant Temp (in/out)

287 / 320 °C

Coolant Flow Rate

8,000–10,000 m³/h

Fuel Enrichment

Up to 4.95% U-235

RPV Height / Diameter

8–9 m / 3.2 m

Reactor Type
Type:PWR / VVER derived
Circuit:Loop-type
Coolant:Light demineralized water
Fuel
Type:UO₂ pellets
Cladding:Zirconium alloy
Enrichment:≤4.95% U-235 (LEU)
RCP Specifications
Flow Rate:4,000–5,000 m³/h
Head:0.8–0.9 MPa
Motor Power:1.6–2.0 MW
MRIA SMPWR Station Cross-Section

Underground Nuclear Island

The cross-section view reveals the key design feature: the reactor pressure vessel and primary circuit components are located below ground level, protected by reinforced concrete structures.

  • Reactor vessel with control rod assemblies
  • Steam generators and pressurizer
  • Emergency core cooling systems
  • Turbine hall and auxiliary systems above ground

Applications

District & Industrial Heat Supply

Providing thermal energy for cities and industrial facilities

Post-War Recovery

Reconstruction and modernization of damaged CHP plants

Critical Infrastructure

Military and security-related facilities

Green Hydrogen Production

Via electrolysis during periods of reduced electricity demand

Hybrid Energy Systems

Integration with renewable energy sources (solar and wind)

Backup Power

Replacement capacity for existing CHPs and thermal power plants

Safety & Security

Underground Placement

The Nuclear Island is designed for underground placement, drastically reducing vulnerability to external threats including:

  • Aerial attacks and blast loads
  • Natural disasters
  • Unauthorized physical access
Safety Features
  • Classical PWR/VVER layout with established safety principles
  • Passive safety characteristics with high thermal and hydraulic inertia
  • Underground placement of Nuclear Island for enhanced protection
  • Specialized high-strength concrete with ballistic and blast-resistance
  • Multi-layer physical protection system (radar, UAV detection, access control)

Development Roadmap

Phase 1
Conceptual & Preparatory
  • Completion of conceptual framework
  • Formation of inter-institutional team
  • Alignment with state authorities
  • Preparation of FOAK site
Phase 2
Design Phase
  • Basic and detailed design documentation
  • Safety and operational solutions
  • Licensing documentation
  • Localization of supply chains
Phase 3
Construction & Commissioning
  • Nuclear and turbine island construction
  • Safety systems installation
  • Cold and hot testing
  • Pilot operation
Phase 4
Scaling & Replication
  • FOAK results analysis
  • Design optimization
  • Serial module deployment
  • Multi-module complexes

Key Partners

SYNERGOATOM SE

Initiator & Governing Body

Czech Republic

WITKOWITZ GROUP

Industrial backbone

Czech Republic

Institute for Nuclear Research

Scientific platform

Ukraine

Sumy State University

Research partner

Ukraine

Czech Technical University

ALLOBOR-5 development

Czech Republic

Member of TRIUMPH Alliance

Офіційні учасники проекту

Провідні наукові та освітні установи України, які формують науково-технічну основу проекту MRIA SMPWR

Summary

MRIA SMPWR represents a transitional technological model designed to address Ukraine's specific energy needs. With a nominal thermal power of ~500 MWt and electrical output of 75-90 MWe, it is optimized for combined heat and power generation.

The concept prioritizes thermal energy production as the primary function, with electricity as a flexible secondary output. Based on proven VVER technology, it offers a path to post-war recovery, energy security, and preparation for future advanced SMR deployment.

Learn More About MRIA SMPWR

Contact us to discuss partnership opportunities in the development of next-generation nuclear technology.

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