Affiliation:
1. Kairos Power LLC , 707 W Tower Ave, Alameda, CA 94501
Abstract
Abstract
Future Gen IV high-temperature reactors are expected to operate above 450 °C where creep effects are significant in safety-related structures, e.g., reactor vessels. The ASME Boiler and Pressure Vessel Code (BPVC) Section III Division 5 provides the rules and methodologies for design of such high-temperature components. Of high relevance to the designer are the isochronous stress–strain curves (ISSCs) part of the rules for deformation limits in the code. The ISSCs are an important method to estimate accumulated inelastic strains at a given stress and duration at elevated temperatures. In this study, the ISSCs for 316H stainless steel in the current edition of the ASME BPVC Section III Division 5 have been reevaluated between 593 °C and 750 °C by adopting a physics-informed minimum creep rate model to reconstruct them. It is demonstrated that the current ASME Section III Division 5 minimum creep rate model underpredicts creep rates compared to experimental data at low stresses (e.g., 650 °C, <40 MPa). By employing a physics-informed minimum creep rate model which captures both diffusive- and dislocation glide/climb-controlled creep regimes, this deficiency is addressed. The ASME ISSCs for 316H stainless steel are then reconstructed by adopting this modified minimum creep rate model. It was found that the ASME ISSCs could underestimate total accumulated strains at ∼σ/σy <0.65 for durations t >1000 h by >10 times which could give rise to non-conservatism in inelastic strain. Experimental data at various temperatures confirm the findings. Potential approaches to address this non-conservatism in inelastic strain and the implications to design are discussed.
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
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