R. D. Carter

TL;DR: In this article, a research program has been undertaken to determine the origins of irradiation-assisted stress corrosion cracking (IASCC) in austenitic alloys in light water reactors, and the effect of impurities on IASCC susceptibility.

TL;DR: In this paper, a combination of STEM and AES data was used to determine the width of the segregated layer in an ultrahigh-purity alloy doped with P. The results showed that the latter is essentially contained in a single monolayer.

TL;DR: In this article, the effect of chromium, phosphorus, silicon and sulfur on the stress corrosion cracking of 304L stainless steel in CERT tests in high purity water or argon at 288°C following irradiation with 3.4 MeV protons at 400°C to 1 dpa, has been investigated using ultrahigh purity alloys (UHP) with controlled impurity additions.

TL;DR: In this article, a technique was developed which addressed the problem of irradiation assisted stress corrosion cracking of stainless steels in light water reactors using high energy protons to induce grain boundary segregation.

TL;DR: In this article, microstructural evolution and deformation behavior of austenitic stainless steels are evaluated for neutron, heavy ion and proton irradiated materials for critical fluence range (0.5 to 10 dpa) where irradiation-assisted stress corrosion cracking susceptibility is observed.