Nuclear Plant Aging Research Articles

Irradiation-assisted stress corrosion cracking as a factor in nuclear power plant aging

Irradiation-assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking (IGSCC) that has occurred infrequently during the last two decades in in-core components of nonsensitized austenitic stainless steel. IASCC is apparently a time-dependent phenomenon, which does not manifest itself until a minimum residence time or threshold fast neutron fluence has been attained in an appropriate material/environment combination. Until now, IASCC has been observed in components that are readily removable, such as fuel rod and absorber tube cladding. The problem is being mitigated in the BWR by alloy impurity control. Hydrogen water chemistry is another highly promising remedy currently under qualification. An extensive effort is underway to improve our understanding of IASCC.

International conference on nuclear power plant aging, availability factor, and reliability analysis

International conference on nuclear power plant aging, availability factor, and reliability analysis