Abstract

A major dilemma facing the nuclear industry is repair or replacement of stainless steel reactor components that have been exposed to neutron irradiation. When conventional fusion welding is used for weld repair, the high temperatures and thermal stresses inherent in the process enhance the growth of helium bubbles, causing intergranular cracking in the heat-affected zone (HAZ). Friction stir processing (FSP) has potential as a weld repair technique for irradiated stainless steel, because it operates at much lower temperatures than fusion welding, and is therefore less likely to cause cracking in the HAZ. Numerical simulation of the FSP process in 304L stainless steel was performed using an Eulerian finite element approach. Model input required flow stresses for the large range of strain rates and temperatures inherent in the FSP process. Temperature predictions in three locations adjacent to the stir zone were accurate to within 4% of experimentally measure values. Prediction of recrystallized grain size at a location about 6mm behind the tool center was less accurate, because the empirical model employed for the prediction did not account for grain growth that occurred after deformation in the experiment was halted.

Highlights

  • The nuclear industry is facing challenges in repair or replacement of stainless steel reactor components, which have been exposed to neutron irradiation

  • When conventional fusion welding is used for weld repair, the high temperatures and thermal stresses inherent in the process enhance the growth of helium bubbles, causing intergranular cracking in the heataffected zone (HAZ) [6,7,8]

  • A tool holder imposed a boundary condition of 19°C on the shank of the tool, which simulated the cooled tool holder on the friction stir processing machine

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Summary

Introduction

The nuclear industry is facing challenges in repair or replacement of stainless steel reactor components, which have been exposed to neutron irradiation. Repair of nuclear components encompasses both the replacement of a failed component, in which case a new component must be joined to existing structures, and the in situ repair of arc welds that have developed stress corrosion cracks in service [2, 9, 10]. In both cases the issue of helium embrittlement, accelerated by the temperatures and stresses of fusion welding, presents a serious difficulty that must be overcome. It is anticipated that many nuclear reactors will function for up to 80 years [12], so the repairability of irradiated stainless steel is of great importance to this industry

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