Cladding structural components with a corrosion resistant material may greatly extend the design life of molten salt reactor concepts. A complete design methodology for such cladded, high temperature nuclear components will require addressing many issues: fabrication, corrosion resistance, metallurgical interaction, and the mechanical interaction of the clad and base materials under load. This work focuses on the final issue: the mechanical interaction of the base and clad under creep-fatigue conditions. Depending on the relative mechanical properties of the two materials the clad may substantially influence the long-term cyclic response of the structural system or its effect might be negligible. To quantify the effect of different clad material properties we develop an efficient method for simulating pressurized cladded components in the limiting case where the section of interest is far from structural discontinuities. Using this method we evaluate the mechanics of the clad/base system and identify different regimes of mechanical response. The focus is on situations relevant to high temperature nuclear components: thermal-cyclic Bree-type problems and similar axisymmetric structures. The insights gained from these structural studies will form the basis for developing design rules for high-temperature, nuclear, cladded components.
The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components
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Messner, MC, Phan, V, Jetter, RI, & Sham, T. "The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components." Proceedings of the ASME 2018 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Prague, Czech Republic. July 15–20, 2018. V01BT01A012. ASME. https://doi.org/10.1115/PVP2018-84101
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