This article examines the understanding of persistent material changes produced in stainless alloys during light water reactor (LWR) irradiation based on the fundamentals of radiation damage and existing experimental measurements. It summarizes the overall trends and correlations for irradiation-assisted stress-corrosion cracking. The article addresses the effects of various radiation factors on corrosion. These include radiation-induced segregation at grain boundaries, radiation hardening, mode of deformation, radiation creep relaxation, and radiolysis. The article discusses a variety of approaches for mitigating stress-corrosion cracking in LWRs, in categories of water chemistry, operating guidelines, new alloys, design issues, and stress mitigation. It concludes with a discussion on the irradiation effects of irradiation on corrosion of zirconium alloys in LWR environments.

This article reviews a series of serious corrosion problems that have plagued the light water reactor (LWR) industry. It discusses the complex corrosion mechanisms involved, and the development of practical engineering solutions for their mitigation. The article contains tables that present the corrosion history of LWRs, and the ten most expensive operation and maintenance costs of corrosion for a particular reactor site.

This article focuses on the environmentally assisted cracking (EAC) of structural materials in boiling water reactors (BWRs), reactor pressure vessels, core internals, and ancillary piping. It discusses the effects of water chemistry on materials degradation, mitigation approaches, and their impact on aging management programs. The article reviews the effects of materials, environment, and stress factors on the cracking susceptibility of ferritic and austenitic structural alloys in BWRs. It describes the methods, such as data-based life-prediction approaches and mechanisms-informed life-prediction approaches, for predicting cracking kinetics in BWRs. The article provides information on several EAC mitigation techniques for BWR components, namely material solutions, stress solutions, and environmental solutions.

Stainless steel alloys have many unique failure mechanisms, including environmentally assisted cracking, cracking associated with welding, and secondary phase embrittlement. This article describes these failure mechanisms and the fracture modes associated with the different categories of stainless steel. These mechanisms and modes are grouped together because of their similarities across the categories.

This article discusses the main materials and water chemistry characteristics of the primary and secondary water circuits of a pressurized water reactor (PWR). It reviews the corrosion issues of PWR materials and the influence of corrosion and fouling on primary and secondary circuit radiation fields. The article explains the primary side intergranular stress corrosion cracking (IGSCC) in different materials, namely, nickel-base alloys, high-strength nickel-base alloys, low-strength austenitic stainless steels, and high-strength stainless steels. The secondary side corrosion in steam generator including denting, pitting, intergranular attack and IGSCC is also discussed. The article examines laboratory studies that have resulted in models and computer codes for evaluating and predicting intergranular corrosion, and considers the remedial actions for preventing or arresting intergranular corrosion. It concludes with information on the external bolting corrosion in nuclear power reactors.

Damage to steels from neutron irradiation affects the properties of steels and is an important factor in the design of safe and economical components for fission and fusion reactors. This article discusses the effects of high-energy neutrons on steels. The effects of damage caused by neutron irradiation include swelling (volume increase), irradiation hardening, and irradiation embrittlement (the influence of irradiation hardening on fracture toughness). These effects are primarily associated with high-energy (greater than 0.1 MeV) neutrons. Consequently, irradiation damage from neutrons is of considerable importance in fast reactors, which produce a significant flux of high-energy neutrons during operation. Irradiation embrittlement must also be considered in the development of ferritic steels for fast reactors and fusion reactors. Although ferritic steels are more resistant to swelling than austenitic steels, irradiation may have a more critical effect on the mechanical properties of ferritic steels.

This article discusses the principles of corrosion and the basis of the various prevention measures that can be taken for different corrosion modes. It describes aqueous corrosion phenomena in terms of the electrochemical reactions that occur at the metal-environment interface. The article explains the specific forms of corrosion, including general corrosion, localized attack, and environmentally assisted cracking. It provides a discussion on the engineering aspects of design that can, without due care and attention, precipitate unexpected premature failure. The article reviews ways to improve corrosion awareness and prevent corrosion/degradation. It describes a life prediction method with an example of environmental degradation in light-water nuclear reactors. The article concludes with a discussion on the validation of life-prediction algorithms and their applications.

This article focuses on the corrosion fatigue testing of steel in high-temperature water and discusses critical experimental issues associated with it. It provides information on the fundamental aspects of environmental crack advancement in general. The article explains the concepts and role of environmentally assisted crack growth in corrosion fatigue. It also discusses the fatigue test methods, including crack initiation testing and crack propagation testing. The article describes the specific types and influence rankings of experimental variables in corrosion fatigue.

This article presents the concept of fracture mechanisms in general terms in order to impart a practical understanding as well as enable readers to develop the ability to identify the basic fracture mechanisms correctly based on microscope observations. The key microscopic features of fracture surfaces are described and illustrated for the important types of fracture mechanisms. It provides a detailed discussion on environmentally assisted crack initiation and growth.

This article provides an overview of how fractographs in this Atlas are organized and presented. It contains a table that lists the distribution content of illustrations for various materials discussed in the Atlas. The causes of fractures for various ferrous and nonferrous alloys and engineered materials are also illustrated.