Course Description

Material selection in nuclear power plants is not merely a design detail; it is a foundational safety and reliability decision. Why? Because nuclear plants create an environment that is uniquely hostile to conventional engineering materials. Inside a reactor pressure vessel, materials must withstand temperatures of 280 to 320 degrees Celsius, pressures of over 150 atmospheres, an intense neutron flux that can exceed ten to the twenty-first neutrons per square centimeter over the plant's life, and highly controlled but still corrosive water chemistry containing boric acid and lithium hydroxide. If you choose the wrong material, the consequences are not merely increased maintenance costs. They include forced outages, expensive component replacements, and in the worst cases, safety events. History provides painful lessons. Primary water stress corrosion cracking in Alloy 600 steam generator tubes has forced the replacement of dozens of steam generators worldwide, costing hundreds of millions of dollars per plant. Irradiation embrittlement of reactor pressure vessel beltline materials has led to neutron fluence limitations and, in some older plants, early retirement. As industrial engineers, you must integrate materials science with system design, inspection planning, and life-cycle cost analysis to ensure safe, long-term operation.

What you'll learn in this course?

• Title: Nuclear Plant Material Selection and Application

• Delivery Method: Online - Self-paced

• Duration: 5 hours (300 minutes)

• CPD Credit: 5 CPD Hours

• Level: Intermediate

• Learners will be able to identify key material degradation mechanisms in nuclear reactor primary and secondary systems.

• Learners will be able to compare the properties of zirconium alloys, stainless steels, nickel-based alloys, and carbon steels used in nuclear plants.

• Learners will be able to explain the role of neutron irradiation on mechanical properties and microstructure of structural materials.

• Learners will be able to apply material selection criteria for reactor pressure vessels, fuel cladding, steam generators, and piping.

• Learners will be able to evaluate corrosion issues such as stress corrosion cracking, irradiation-assisted stress corrosion cracking, and flow-accelerated corrosion.

Prerequisites

• Basic engineering knowledge and familiarity with nuclear systems, radiation safety, and engineering units