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The Joint Research Centre: EU Science Hub
Small modular reactors

Small modular reactors and innovative reactor systems

Contributes to European Commission priorities

Portfolio overview

Advanced nuclear reactors, particularly small modular reactors (SMRs), are being designed for improved sustainability, economics, safety and security. They are also gaining increasing attention for the delivery of clean power and heat.  

This portfolio supports their development and deployment. It provides policymakers with a realistic view of how SMRs and other innovative reactor systems can complement the European energy mix. It ensures that dedicated policy options are evidence-based, and it supports the work of the new European Industrial Alliance on SMRs, the Sustainable Nuclear Energy Technology Platform and the Generation IV International Forum.   

 

Objectives

  • Evaluate safety and sustainability of small modular reactors design

    Assess different designs of small modular reactors (SMRs), innovative reactors and fuels, in terms of safety, viability and sustainability.  

  • Promote early integration of safety, safeguards and security 

    Aim to ensure that designers and vendor companies integrate safety, safeguards and security constraints early in the design process, thereby facilitating and accelerating licensing.  

  • Integrate nuclear technologies and non-electric applications in energy modelling 

    Provide policymakers with a realistic view of how SMRs and other innovative reactor systems and their applications can complement the European energy mix, together with renewables.

  • Support the improvement of data and standards  

    Contribute to EU efforts to improve existing data, codes and standards for the design, manufacturing and in-service inspection of SMRs.  

  • Help to establish a European supply chain 

    Support the creation of a European supply chain for safety-related structures, systems and components.  

Scientific tools

Instrument for the thermal, mechanical and neutron-physical analysis of a cylindrical fuel rod in nuclear reactors.

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