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CLADDING · BIMETAL PRODUCT · BIMETAL PRESSURE VESSEL TECHNICAL STUDY

Numerical Simulation of Fatigue Crack Propagation on the Surface of Weld Overlay Layer in Hot-Wall Hydrogenation Reactors

Literature Overview and Research Background

The hot-wall hydrogenation reactor is a critical piece of equipment in the petrochemical industry, typically constructed with a carbon steel or low-alloy steel base metal overlaid with a nickel-based alloy (such as Inconel 625 or Alloy 600) to resist high-temperature hydrogen attack and corrosion. The weld overlay layer, usually fabricated by electroslag welding (ESW) or submerged arc welding (SAW), is subjected to cyclic thermal and mechanical loading during normal operation. Surface cracks in the overlay layer, whether initiated during fabrication or during service, can propagate under fatigue loading and ultimately lead to catastrophic failure. This study employs finite element analysis (FEA) combined with fracture mechanics to simulate the fatigue crack propagation behavior on the surface of the weld overlay layer, providing a quantitative basis for remaining life assessment and inspection interval optimization.

Core Technical Approach and Methodology

The numerical simulation framework integrates the J-integral method with Paris' law for crack growth prediction. The model considers the actual geometry of the reactor shell, the residual stress field induced by the multi-pass overlay welding process, and the cyclic stress amplitude experienced during pressure cycling. Key input parameters include the stress intensity factor range (ΔK), the fatigue crack growth rate (da/dN), and the threshold value (ΔKth) for the specific overlay alloy. The study also accounts for the effect of microstructural heterogeneity in the overlay layer—columnar grains near the base metal/overlay interface versus equiaxed grains near the surface—which influences the effective crack growth resistance.

Key Simulation Parameters

Parameter Typical Value Source / Basis
Overlay alloy Inconel 625 Common for hot-wall reactors
Overlay thickness 6–12 mm Per NB/T 47014 and API 934
Base metal 1.25Cr-0.5Mo steel Typical reactor shell material
ΔK range 10–80 MPa·m^0.5 Based on operating pressure cycles
ΔKth 8–12 MPa·m^0.5 Literature value for Inconel 625
Stress ratio (R) 0.3–0.7 Pressure cycling condition
Number of cycles 10^5–10^7 Design life consideration

Interpretation of Key Findings

The simulation results reveal that surface cracks in the overlay layer propagate in a manner strongly influenced by the residual stress distribution from the welding process. The tensile residual stresses near the surface accelerate crack initiation and early-stage propagation, while compressive residual stresses deeper in the overlay layer can retard crack growth once the crack extends below the neutral axis. The study demonstrates that the fatigue crack growth rate in the overlay layer is generally lower than that of the base metal due to the superior fatigue properties of the nickel-based alloy, but the presence of weld defects such as lack of fusion or porosity at the overlay/base metal interface can serve as preferential crack initiation sites.

The research also highlights the importance of the constraint effect on crack propagation. Surface cracks in a thin overlay layer experience a different constraint state compared to through-thickness cracks, leading to deviations from plane-strain fracture mechanics predictions. The J-integral approach, which does not assume a specific crack geometry, provides more accurate results for the curved surface geometry of the reactor shell.

Engineering Practice Integration

From a practical standpoint, this study has direct implications for the inspection and maintenance strategy of hot-wall hydrogenation reactors. The predicted crack growth rates can be used to establish rational inspection intervals based on the expected number of pressure cycles between turnarounds. For reactors operating under frequent start-up and shutdown conditions, the fatigue crack growth in the overlay layer becomes a dominant failure mode that must be considered in fitness-for-service assessments per API 579-1/ASME FFS-1.

The findings also support the recommendation for post-weld heat treatment (PWHT) of the overlay layer to relieve residual stresses, thereby reducing the driving force for fatigue crack initiation and growth. However, PWHT must be performed with care to avoid sensitization of the nickel-based overlay alloy, which could compromise its corrosion resistance.

Key Questions and Reflections

A critical question raised by this study is the validity of applying single-crack fracture mechanics to an overlay layer that may contain multiple surface defects. In practice, overlay layers often have several surface indications detected by magnetic particle testing (MT) or ultrasonic testing (UT). The interaction between multiple cracks and the resulting shielding effects are not fully captured in the single-crack simulation model. Additionally, the study does not explicitly address the effect of high-temperature creep-fatigue interaction, which is relevant for reactors operating above 400°C.

Another important consideration is the representativeness of the material properties used in the simulation. The fatigue crack growth behavior of the overlay layer is highly dependent on the welding process parameters, which affect the microstructure and, consequently, the fracture toughness. A single set of material properties may not adequately represent the variability across different reactors or even different sections of the same reactor.

Study Insights and Implications

This literature provides a valuable quantitative framework for understanding fatigue crack propagation in weld overlay layers under realistic operating conditions. The integration of residual stress effects, microstructural heterogeneity, and geometric constraints into the numerical model represents a significant advancement over simpler analytical approaches. For engineers involved in the design, fabrication, and integrity assessment of hot-wall hydrogenation reactors, the key takeaway is that fatigue crack growth in the overlay layer should be explicitly considered in the design life assessment, particularly for reactors subject to frequent thermal cycling.

The study reinforces the importance of rigorous quality control during overlay welding, including strict control of welding parameters to minimize defects at the overlay/base metal interface, thorough non-destructive examination of the overlay layer, and appropriate post-weld heat treatment. It also underscores the need for continued research into multi-crack interaction effects and creep-fatigue interaction at elevated temperatures to further refine the predictive capabilities of the model.