A design approach along with design rules for cladded components for high temperature nuclear service will be provided in another PVP paper. The proposed design method guards the clad material against the creep-fatigue failure and ratcheting strain accumulation in elevated temperature nuclear service without the requirement of long-term material properties. However, it limits the type of clad materials that can be used with the existing Class A materials qualified for ASME Section III, Division 5 rules. The analysis approach and design rules allow the use of two types of clad materials – soft clads that creep much faster than the base material and hard clads that creep much slower and has higher yield stress than the base material. This paper develops the selection criteria for such soft and hard clad materials to use with a Class A metallic alloy – austenitic steel 316H. The criteria will be developed based on the effect of relative elastic modulus and minimum creep rate on the long term stress redistribution between the 316H base and the clad material. The paper will also discuss assumptions made for the stress redistribution study and provide example calculations for categorizing several materials as soft or hard clad versus a 316H base material.


Selection Criteria for Clad Materials to Use With a 316h Base Material for High Temperature Nuclear Reactor Cladded Components

Division / Sponsors: 
Pressure Vessels & Piping (PVP)


Paper Proceedings: https://asmedigitalcollection.asme.org/PVP/PVP2020/volume/83815

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