Project results are expected to contribute to some of the following outcomes:

• Development of know-how and tools for the improvement of safety in relation to the design and safe operation of Nuclear Power Plants (NPPs) and Research Reactors, including resistance against natural and anthropocentric impacts, conditions for long-term operations, enhanced accident tolerant fuels, and preparedness for nuclear and radiological emergency, response and recovery (synergies with the European Partnership for research in radiation protection and detection of ionising radiation (Topic HORIZON-EURATOM-2021-NRT-01-09) should be fostered).
• Development of methods and tools for operational innovation and digital transition (e.g. I&C) and for ensuring availability of systems, structures and components, including fuel assemblies, needed for reliable and safe operation of NPPs.
• Development of methods and tools for maintenance (Non-Destructive Testing, repair, replacement, chemical cleaning), and for monitoring, preventing and mitigating the ageing effects of structural materials and components, for long-term operation, including the use of advanced models based on state-of-the-art computational techniques. Uncertainties assessment will also be included.
• Development of methods and tools for core and plant advanced surveillance, monitoring, diagnostics and prognostics.
• Development of tools and methods for improvement of the capabilities and safety of NPPs in the transition to future low-carbon and smart energy systems, and in flexible operation.
• Development and use of deterministic and risk assessment methods improving safety, reliability and availability of active and passive systems for present reactors, reinforcing NPP safety provisions through a better understanding of some predominant phenomena with the fundamental support of experimentation.
• Update of the Severe Accident Management Guidelines and experimental research on severe accident prevention and mitigation mechanisms (e.g. passive phenomenology) and aiming at “practical” elimination of risks associated with an extended core melt or spent fuel damage for all reactors currently in operation in EU and for reactors to be licensed for design-life extensions, i.e. long-term operation.
• Preparation of recommendations, tools and guidelines for knowledge management to maintain know-how and for implementation of actions dedicated to maximise safety-related return from experience.
• Preparation of recommendations for calculations and tests which could be usefully performed on NPPs before decommissioning, and for calculations and tests required to be performed on crucial NPP components after decommissioning in relation to the validation of ageing models.
• Effective promotion of a safety culture, integration of human factor in safety assessment, inclusion of research needs of Member States’ nuclear safety regulators, supporting implementation of training requirements of the Nuclear Safety Directive^[1].

Development of nuclear safety culture in publics and authorities other than the nuclear safety regulators.

To achieve the general objectives of the Programme^[2], the proposed research should aim at developing knowledge, tools and guidelines supporting safe operation of existing nuclear power plants and research reactors, including long-term operation and management of fuel with increased nuclear fuel burnup and enrichment, and allowing for knowledge-based decisions by operators and regulators. Advanced safety systems for existing Generation II and III nuclear plants could also be included in research proposals, especially with new build.

Research could include safe and trusted AI-enabled core monitoring/diagnostics, integrity assessments of systems, structures and components, in-service inspection and qualification, definition of updated integrity requirements, load quantification, evaluation of ageing and reliability of components of different systems. It could also address different types of materials such as metals, non-metallic, concrete, composites or polymers, ceramic and fuels, using suitable tools and models, digital transition, long-term operation and other innovations e.g. Accident Tolerant Fuel (ATF).

Activities could include the development and use of models and codes for probabilistic safety assessments (PSA) and deterministic safety assessments (DSA) of plant safety-related transients, use of advanced integrated safety methodologies (including better simulation methods and consideration of ageing effects), assessment of operational margins and upgraded reactor safety systems (increased diversification and robustness), criticality studies as well as seismic, flooding and fire propagation modelling. Use of PSA techniques in periodic safety review (PSR) of nuclear power plants, for prioritisation of the improvement actions for each one of the 16 safety factors, as provided in IAEA specific safety guide for periodic safety review for nuclear power plants (SSG-25)^[3].

Specific attention could be paid to solutions taking into account external hazards linked to most recent climate projections. Another important aspect is integration of human factor (cultural, behavioural and organisational aspects) and safety culture-related issues in safety assessment.

Proposed research could also address challenges for mitigating severe accidents, which are related to in-vessel and ex-vessel corium/debris coolability and interactions, containment behaviour including hydrogen explosion risks, evaluation of the source term for any potential radioactive releases, potential impact on the environment and evaluation of scenarios should a severe accident occur, emergency preparedness and response, development and use of computational techniques based on big data and artificial intelligence to perform sensitivity and uncertainty analyses.

The Commission would also invite consortia to propose innovative solutions and research approaches other than those listed above in order to deliver the expected outcomes.

Due to the scope of this topic, international cooperation is encouraged, in particular to avoid any duplication of the work conducted in other fora.

Where appropriate, the Commission recommends that consortia make use of the services of the Joint Research Centre (JRC). The JRC may participate in the preparation and submission of the proposal. The JRC would bear the operational costs for its staff and research infrastructure. The JRC facilities and expertise are listed in General Annex H of this Work Programme.

[1] Council Directive 2009/71/Euratom of 25 June 2009 establishing a Community framework for the nuclear safety of nuclear installations amended by Council Directive 2014/87/Euratom of 8 July 2014

[2] Art. 3(1) of the Council Regulation: The general objective of the Euratom Programme is to pursue nuclear research and training activities, with an emphasis on the continuous improvement of nuclear safety, security and radiation protection, as well as to complement the achievement of Horizon Europe’s objectives inter alia in the context of the energy transition.

[3] For details see https://www.iaea.org/publications/8911/periodic-safety-review-for-nuclear-power-plants