D
D. L. Damcott
Researcher at University of Michigan
Publications - 12
Citations - 292
D. L. Damcott is an academic researcher from University of Michigan. The author has contributed to research in topics: Grain boundary & Alloy. The author has an hindex of 7, co-authored 12 publications receiving 284 citations. Previous affiliations of D. L. Damcott include Massachusetts Institute of Technology.
Papers
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Journal ArticleDOI
Microchemistry and microstructure of proton-irradiated austenitic alloys: toward an understanding of irradiation effects in LWR core components
Gary S. Was,Todd R. Allen,J. T. Busby,Jian Gan,D. L. Damcott,D. Carter,Michael Atzmon,Edward A. Kenik +7 more
TL;DR: In this article, the effect of radiation induced segregation (RIS) and microstructure development on grain boundary composition and micro-structural development has been investigated, and it was found that RIS is related to the development of dislocation and void microstructures.
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Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys
TL;DR: In this article, the authors used Auger electron spectroscopy of grain boundary facets exposed in situ to measure grain boundary composition and found that grain boundary Ni increased and Cr decreased sharply below 1 dpa and achieved near-saturation between 1 and 3 dpa.
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Effects of proton irradiation on the microstructure and microchemistry of type 304L stainless steel
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.
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Quantitative analysis of radiation-induced grain-boundary segregation measurements
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.
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Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels
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.