Work Plan

The work to be accomplished in NuMaP is partitioned into five work packages (WP). Below, a brief description of each work package is given, together with a list of associated tasks.

The work package leaders (WPL) of NuMaP are:

Pär Olsson - WP1, Management
Gunnar Westin - WP2, Fabrication & Characterization
Xiaoqing Li - WP3, Modeling & Design
Farid Akhtar - WP4, Exposure & Testing
Irma Heikkilä - WP5, Qualification

WP1: Management

WP1 oversees the overall coordination and management of the project, bringing together representatives from each partner along with junior members to ensure balanced participation. It establishes and maintains the work structure, supports recruitment with a focus on diversity, and organizes regular meetings at both project-wide and work package levels. The group also manages dissemination through scientific publications, public outreach, and media engagement. In addition, WP1 handles intellectual property and exploitation in line with consortium agreements and regulations. Finally, it facilitates access for external researchers by developing guidelines and supporting collaboration through dedicated resources.

WP2: Fabrication & Characterization

WP2 focuses on advanced materials development through several specialized subgroups. It includes the synthesis of nano-phase and high-purity metal nitrides and carbides for nuclear and liquid metal applications, as well as the optimization of alumina-forming martensitic steels for improved performance and durability. The work also covers post-irradiation examination using advanced characterization techniques to study material evolution. In addition, efforts are made to develop new synthesis routes for uranium nitride from UF₆. Finally, the WP explores protective PVD coatings for cladding materials, enhancing resistance to corrosion, wear, and high-temperature reactor conditions.

Microstructure of NbC-Ni0.85Nb0.15 composite powders.

Experimental AFA-alloy (10Cr-10Ni-3Al based alloy) exposed to liquid lead at 550°C for 1800 hours, no sign of corrosion, only a thin protective Al-rich oxide is visible on the exposed surface.

WP3: Modeling & Design

WP3 works on computational modeling across multiple scales to understand and predict material behavior under nuclear conditions. Its subgroups investigate micromechanical properties at the atomic level, including deformation, defects, and fracture mechanisms using advanced ab initio methods and machine learning. The WP also models irradiation effects in protective coatings, guiding experiments and improving performance under reactor conditions. In addition, it explores fracture mechanics in nuclear fuels, assessing the role of impurities and microstructure. Finally, multi-scale approaches are used to study radiation damage and diffusion in bulk materials and interfaces, supporting experimental efforts and improving fundamental understanding.

(left) Isothermal elastic moduli for CLAM (ab initio modeling) and a RAFM steel (experiment). (right) Predicted alloying effect in CLAM with respect to pure Fe.

(left) Impurity sites in the most stable tilt and twist grain boundaries in UO2. (right) Preliminary results for weakening effect of Xe (gas) and Mo (solid) fission products in UO2.

WP4:Exposure & Testing

WP4 focuses on experimental testing and validation of advanced materials under realistic and accelerated reactor conditions, structured across several subgroups. It includes ion irradiation studies to simulate neutron damage and assess microstructural evolution. The WP also develops specialized platforms to investigate high-temperature tribo-corrosion and erosion-corrosion processes in liquid metal environments. Mechanical testing evaluates material performance, including embrittlement and creep-rupture behavior of advanced steels and cladding systems. Additionally, long-term stability and corrosion of fuel cladding are studied under radiation and environmental exposure. Overall, WP4 provides critical insights into material durability, degradation mechanisms, and performance in nuclear applications.

Sketch layout of the UU Tandem ion beam laboratory.

(a) Friction for 316L in liquid Pb at 550 °C, (b) 3D wear morphology of 316L, (c) and (d) SEM of surface layer formed after fretting at 550°C in liquid Pb.

WP5: Qualification

WP5 addresses the process development and qualification of key reactor materials and components through several targeted subgroups. It includes the development of improved fuel processing routes to enhance recyclability and efficiency. The WP also supports the qualification of critical components such as impellers, blades, and steam generator tubes under realistic operating conditions. Advanced manufacturing and coating techniques are evaluated to ensure durability and corrosion resistance in liquid metal environments. In addition, high-accuracy thermal property measurements are established to support material certification. Overall, WP5 bridges research and industrial application, advancing technologies toward deployment readiness.