Hi-fidelity characterisation of molten salt - graphite pore interactions through experiments and embedded modelling

Started

Nuclear Fission and Fusion(Nuclear Fission, Nuclear supporting technologies)

Basic and strategic applied research

PHYSICAL SCIENCES AND MATHEMATICS (Chemistry)
PHYSICAL SCIENCES AND MATHEMATICS (Metallurgy and Materials)

Not Cross-cutting

Dr A Theodosiou
The University of Manchester

Standard

EPSRC

13 January 2025

12 January 2028

36 months

£826,733

Energy

North West

Energy and Decarbonisation

Dr A Theodosiou, The University of Manchester

Dr A Jones, Mechanical, Aerospace and Civil Engineering, University of Manchester
Dr CA Sharrad, Chemical Engineering and Analytical Science, University of Manchester

Graphitic components are subjected to fast neutron flux in a molten salt reactor (MSR) for several years and there is a potential for salt or fuel salt infiltration into the bulk graphitic regions. Salt infiltration is generally considered to be unfavourable or harmful to the operation of an MSR due to the potential for graphite degradation, transport of fission products such as 135Xe that can decrease moderation, generation of hotspots, and fuel inventory change. In general, salt permeation and transport, which are dependent on the salt thermodynamics and kinetics, depend critically on the pore/crack shape, morphology and interconnectivity that are not yet well-elucidated. We propose a suite of fuel salt (FLiBe with U) infiltration experiments followed by X-ray computed tomography, mechanical property evaluation, and high-fidelity data analytics and modelling along with complimentary porosimetry measurements and XPS analysis. Three graphite grades are selected in this project: NBG-18, IG-110 and POCO: ZXF-5Q; the selected grades will cover the typical porosities observed in nuclear graphite. The main objective of our investigation is to draw out the differences in fuel salt infiltration behaviour in the selected graphite grades and assess the change in mechanical properties. We anticipate that our work will assist in selecting nuclear graphite grades optimized for the current and advanced MSRs

25/06/25