ABOUT THE PROJECT
The context
Research Reactors (RRs) are vital to advancing nuclear science and technology, producing
medical
isotopes for healthcare, and supporting education and training in nuclear fields.
These reactors
provide critical infrastructure for material testing, neutron scattering, and radiography,
offering significant socio-economic benefits that contribute to sustainable development
worldwide.
Most of Europe’s RRs have been in operation for over 60 years, approaching the
end of their
original design lifetimes. While new facilities are under construction, they will only partially
replace the required capacity. The ageing reactors face challenges related to material
degradation primarily due to radiation-induced damage, threatening their long-term
functionality.
Ensuring the continued safe operation (CSO) of these reactors is essential to maintaining their
role in nuclear research, the global supply of medical isotopes, and the development of
next-generation nuclear technologies. Addressing these challenges requires a deeper
understanding of the degradation of materials and components critical to reactor safety and
advanced ageing management strategies.
Objectives
Improve the current understanding of the irradiation-induced degradation behaviour and corrosion mechanisms in aluminium alloys in RRs.
Filling the existing knowledge and data gaps on this topic will contribute to the safe continued operation of Research Reactors and will also provide valuable input for the design of future RRs. To achieve this, the following objectives are defined:
- Quantitative characterisation of hardening and toughness reduction of Al alloys, as a function of thermal neutron fluence and alloy composition.
- Investigation of radiation damage on the microstructures of the different RR materials and correlation to the changes in mechanical properties.
- Development of predictive models for irradiation damage in RR materials.
- Improve the current understanding on the corrosion behaviour of aluminium alloys during operation conditions and evaluate the effectiveness of prevention and mitigation strategies.
Validate the use of sub-size specimens to monitor the radiation-induced embrittlement of Al alloys in the surveillance programs of RRs
In order to achieve this, specific objectives are needed. Within these objectives, the dialogue between experiments and numerical simulations based on Finite Element Modelling (FEM) is contemplated:
- FEM study of specimen size effect on fracture toughness initiation and propagation on as-received and irradiated Al alloys.
- Experimental investigation of irradiation embrittlement of several RR Al alloys using sub-sized specimens.
To achieve this, some objectives have been defined:
- Comparison of the national rules and codes, the presently used practices dealing with safety and ageing management of the RRs to determine and fill the gaps.
- Elaborate recommendations to the National Regulatory Committees regarding the upgrade of RRs safety rules and guidelines.
- Initiate European level research program on ageing and structural integrity of RRs for EU excellence and competence development.
Impacts
Contributing to Safety and Innovation
Magic-RR is dedicated to ensuring the continued safe operation (CSO) of ageing Research
Reactors (RRs). By studying the degradation mechanisms of materials, such as aluminium
alloys, the project supports the implementation of the highest safety standards
under the
Nuclear Safety Directive.
This work will help RR operators, developers, and regulators ensure compliance with safety
regulations and improve the operational lifespan of these critical
infrastructures.
Strategic and Economic Benefits
The project strengthens Europe’s innovation capacity and competitiveness in research
reactor
technology. By integrating new knowledge on material behaviour, advanced
testing methods,
and predictive modelling, Magic-RR supports the design of safer, more efficient
reactors.
These advancements open new opportunities for R&D institutes and utilities, reduce
costs
through improved ageing management, and minimise reactor
shutdowns, boosting productivity
and ensuring reliable supply chains, including medical isotopes.
Environmental and Societal Impact
Research Reactors are essential for Europe’s energy transition, contributing to the
decarbonisation targets outlined in the European Energy Roadmap 2050. Magic-RR
supports the
long-term operation of reactors that play a key role in material qualification for
next-generation nuclear systems.
Additionally, the project secures the supply of medical isotopes vital for
healthcare,
bridging the gap until new facilities like PALLAS and JHR become operational.
Advancing Scientific Excellence
Magic-RR generates groundbreaking insights into irradiation and corrosion damage in
aluminium alloys, developing advanced multi-scale models for predicting
material
degradation.
These results are expected to have a high scientific impact, with findings published
in
leading international journals, advancing global knowledge in nuclear materials
science.
Work areas
- 1
- 2
- 3
- 4
- 5
This work area is dedicated to perform the reference and PIE testing, microstructural
characterisation of selected aluminium alloys used
in Research Reactors (RRs), corrosion testing and multiscale modelling of irradiation damage
in Al alloys.
Sub-focus areas:
- Irradiation damage mechanisms in RR materials.
- Corrosion behaviour of Al alloys: Prevention and mitigation strategies.
- Modeling of irradiation damage.
This work area is focused on an experimental – numerical approach for validation of sub-size
specimens for surveillance testing
of RRs.
Sub-focus areas:
- Experimental validation of sub-size specimens for surveillance programs: assessment of hardening based on sub-sized tensile specimens and assessment of fracture toughness based on sub-size C(T) specimens.
- Numerical modeling to account for size effects on fracture toughness determination.
This work area is dedicated to the ageing management methods of RRs.
Sub-focus areas:
- Ageing management methods of RRs to support LTO.
- Best practice guidelines on ageing management and structural integrity.
This work area will focus on a proper communication and dissemination of the project
results.
Sub-focus areas:
- Public Communication.
- Dissemination plan, interaction with stakeholders and publications.
- Dissemination, Education and Training.
This work area will ensure a proper management of the project.
Sub-focus areas:
- Project coordination.
- Project office.
- Scientific Advisory Board (SAB).