Abstract
Austenitic stainless steels are one of the most important alloy systems used as structural components in current and future nuclear reactor systems. This chapter reviews the physical and mechanical behavior of stainless steels in the reactor environment. Radiation-induced metallurgical changes include radiation-induced segregation, dislocation loop formation, phase stability, and transmutation. Radiation-induced mechanical property changes reviewed include hardening, fracture toughness, embrittlement, swelling, creep, and fatigue. The interaction of stainless steel with the environment is also important and fuel-clad chemical interaction in fast reactors is covered, along with chemical compatibility with the water coolant in light water reactors. Degradation modes include stress-corrosion cracking, irradiation-assisted stress-corrosion cracking, and irradiation-accelerated corrosion. Stainless steels are likely to continue to be important in light water reactors with life extension as well as small modular reactors and many Generation IV (GenIV) reactor systems.
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