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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Mechanical Strength of Explosion Welded Thin Stainless-steel Cladding on Carbon Steel
Author(s) Nathan Clark Reid, Lauren Garrison, John Echols, Kaustubh Bawane, Jean Paul Allain
On-Site Speaker (Planned) Nathan Clark Reid
Abstract Scope Stainless-steel cladding plates have become increasingly popular for in-vessel components in both nuclear fission pressure vessel components as well as for nuclear fusion structural components in the blanket module. It utilizes the advantages of limiting expensive alloying elements and high activation at end-of-life while providing a corrosion resistant layer. In joining two dissimilar metals, the interface must be sufficiently bonded to avoid failure via interfacial delamination. The interfacial bond strength is the limiting factor in strength of these components under the stresses induced by load bearing and thermal gradients. Mechanical testing is performed to characterize the explosion welding of AISI 347 stainless cladding to a grade 70 carbon steel base. Compression shear testing is used to define the parameters for a tensile lap-shear testing for miniaturized neutron-irradiated tensile specimens. The composite strength is tested by impact and flexural testing. Fracture surface analysis is conducted to identify the modes of failure.
Proceedings Inclusion? Planned:
Keywords Joining, Mechanical Properties, Nuclear Materials

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Development of PVD Cr Coatings for Hydrothermal Corrosion Mitigation of SiC-SiCf Fuel Cladding in LWRs
Development of UN/UO2 Composite Fuels for LWR Applications
Enhanced Microstructural Stability of ARB-processed Cu/Nb Nanolayers Under Heavy Dose Ion Irradiation at Elevated Temperatures
Evaluation and Irradiation of 14YWT Capacitive Discharge Resistance Welds
Experimental Characterisation of the Variation of Local Residual Stresses in TRISO Coatings
Fabrication, Characterisation and Oxidation Resistance of an Innovative Composite Fuel: UN Microspheres Embedded in UO2 Matrix
Improved Techniques for Determining Local Thermal Transport in Composite Nuclear Fuels
Irradiation Induced Forced Chemical Mixing and Local Hardening in Mechanically-processed Immiscible Zr/Nb Multilayers
Mechanical Strength of Explosion Welded Thin Stainless-steel Cladding on Carbon Steel
Novel Fiber Fretting Technique for Tribological Properties of Composite Interphases
Opportunities for Nanostructured Tungsten Alloys in Composite Fusion Materials
Overview of the Westinghouse Accident Tolerant and High Burnup Fuel Program
Post-irradiation Examinations of TRISO Particles Corroded in Molten FLiBe Salt under Neutron Irradiation
Radiation Tolerance and Microstructural Changes of Nanocrystalline Cu-Ta Alloy to High Dose Self-ion Irradiation
SiGA SiC-SiC Composites Development for Accident Tolerant Fuel
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Tungsten-based High and Medium Entropy Alloys and Composites for Nuclear Applications
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