The Project: Work Packages
WP1
Reactor concepts, critical analysis
and exploitation
WP1 is aimed at acting as interface between the MSR designer and the work performed in the project. Analysis relevant to the general compliance to the EU directives could be considered. WP1 Actvities: 
Providing information regarding different EU MSR designs to allow the analyses performed in other WPs; Performing a critical analysis to identify the related scientific locks and R&D needs for the different CTEs selected in the project. Concepts based both on fluoride and chloride salts will be considered, together with breeder and burner MSR versions; Developing a database to be used in the analyses and calculations of WP4, WP5 and WP6; Analysing the outcomes of each single WP and providing future perspective on the MSR technology; Development through the preparation of a road map; Exploiting the results of the project also through a stakeholder group with external end-users.
WP2
Chemistry of fuel salt and structural materials in reactor environment
WP2 is aimed at providing experimental data and models on density, viscosity, and thermal conductivity of fission products systems, i.e., systems representative of irradiated fuel salt. Regarding the corrosion phenomena of the reactor core structural material, the WP will address the combined effects of salt corrosion with respect to mechanical stress and irradiation. WP2 Activities: Organize a round robin campaign on thermo-physical property measurements of salts; Define best practices for accurate measurements of thermochemical and thermophysical properties; Develop a density and viscosity database coupled to the JRCMSD; Provide information in actual fission product behaviour (volatilization, deposition) under MSR-representative conditions. Gain insight into the combined effects of structural material corrosion and mechanical stresses.
CTE1: CHEMISTRY OF FUEL SALT AND STRUCTURAL MATERIAL IN REACTOR ENVIRONMENT
WP3
Experiments on phenomena relevant for safety
WP3 is aimed at increasing the knowledge of the phenomena that are relevant for safety-related components (e.g., passive safety systems, safety functions, …). WP3 Activities: Validate numerical models for the transport of the solid fission products, deposition on the structural components and interaction with bubbling system; Assess the stability of natural convection in 3D geometry with molten salts; Define specification requirements for large experimental facilities for MSRs.
CTE2: EXPERIMENTAL EVIDENCE ON SAFETY RELATED PHENOMENA
WP4
Modelling and simulations to enable safety assessment and licensing
WP4 helps to enable the compatibility of design studies and problem-oriented R&D with the European regulatory environment. It considers the involvement of comprehensive simulations directly in the safety assessment process, if practical experience feedback might be considered as poor or limited. WP4 Activities: PIRT study to enhance the understanding of safety-related processes and factors that should be simulated + Target Accuracy Requirements; Develop computational chains combing well-elaborated system codes and high fidelity to estimate uncertainties of such modeling; Develop and perform relevant numerical and experiment-based benchmarks Demonstrate the maturity of the predictive capabilities of the modelling and simulation tools experience with modelling and simulation and the feasibility to compensate the lack of practical a graded approach to the safety assessment.
CTE3: MODELLING PREPAREDNESS FOR SAFETY AND LICENSING
WP5
MSR sustainability
The WP5 is aimed at contributing to the evaluation of the sustainability, proliferation resistance and safeguardability of the fuel cycle options and reprocessing schemes for MSR. WP5 Activities: Providing standardized methods to preliminary assess sustainability of fuel cycle performance of MSR concept; Simulating the detailed nuclides flow inside the MSR system; Analysis of possible salt clean-up and reprocessing techniques to assess their efficiency, pace and proliferation resistance; Assessing alternative passive method for salt clean-up; Simulating the radionuclide releases from fuel salt during nominal condition and at elevated salt temperature; Evaluating the proliferation resistance and safeguardability of different reprocessing schemes and fuel cycle options.
CTE4: SUSTAINABILITY & SAFEGUARDS COMPLIANCE OF MSR FUEL CYCLE
WP6
Safety aspects of MSR flexibility
The WP6 is aimed at analysing the safety aspects of the MSR flexibility in terms of
operation and cogeneration requirements to safely adopt the MSR in an energy mix
with intermittent energy sources. WP6 Activities: Highlight the operation strategy, potential limitations and opportunities for flexible use of MSRs; Select cogeneration options for MSR systems and define energy conversion system configurations to cope with non-electrical end-usages; Enhance and extend the numerical simulation tools to analyse the whole plant configuration arrangement and take into account the operating conditions and the plant dynamics situations to consider; Identify specific safety issues coming from flexibility performance from a functional safety analysis perspective.
CTE5: DEMONSTRATION OF SAFE MSR ADAPTABILITY IN FUTURE DECARBONIZED ENERGY SCENARIO