Zobrazeno 1 - 10
of 57
pro vyhledávání: '"Edward P. Simonen"'
Publikováno v:
Philosophical Magazine. 85:609-617
Post-irradiation annealing studies indicate small defect clusters may be a potential contributor to IASCC. In this study, small defect clusters and their behavior during annealing are examined. A CP-304 SS alloy was irradiated with 3.2 MeV protons to
Publikováno v:
Journal of Nuclear Materials. 325:94-106
The effect of the oversized hafnium or platinum (0.3 at.%) solutes on the evolution of irradiated microstructure in 316SS was investigated. Irradiations were conducted with 5 MeV Ni-ions at 500 °C to doses up to 50 dpa or with 3.2 MeV protons at 400
Publikováno v:
Journal of Nuclear Materials. 321:192-209
The influence of oversized solute additions on the radiation-induced microstructure, radiation-induced segregation (RIS) at grain boundaries and post-irradiation intergranular stress corrosion cracking (IGSCC) behavior of model, high-purity 316 stain
Autor:
Brian M. Oliver, Edward P. Simonen, Francis A. Garner, Danny J. Edwards, Stephen M. Bruemmer, Lawrence R. Greenwood
Publikováno v:
Journal of Nuclear Materials. 317:32-45
A cold worked 316SS baffle bolt was extracted from the Tihange pressurized water reactor and sectioned at three different positions. The temperature and dose at the 1-mm bolt head position were 593 K and 19.5 dpa respectively, whereas at two shank po
Publikováno v:
Journal of Nuclear Materials. 317:13-31
Six austenitic stainless steel heats (three heats each of 304SS and 316SS) neutron-irradiated at 275 °C from 0.6 to 13.3 dpa have been carefully characterized by TEM and their hardness measured as a function of dose. The characterization revealed th
Publikováno v:
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
Radiation effects on grain boundary microchemistry and near grain boundary microstructure is of critical importance for understanding irradiation-assisted stress corrosion cracking (IASCC) of light-water reactor (LWR) core internals. Radiation-induce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b841ed4d35802a76cd8409e2e8ccf6cb
https://doi.org/10.1002/9781118787618.ch116
https://doi.org/10.1002/9781118787618.ch116
Publikováno v:
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::045c6b7c3acad2d2d0ef2b72cf578e98
https://doi.org/10.1002/9781118787618.ch105
https://doi.org/10.1002/9781118787618.ch105
Autor:
Russell H. Jones, G.E. Youngblood, Charles H. Henager, Edward P. Simonen, Charles A. Lewinsohn
Publikováno v:
Journal of Nuclear Materials. :584-587
Silicon carbide has many properties that are attractive for applications in fusion energy systems. The reliability of monolithic silicon carbide, however, is insufficient for its use in large components. Ceramic matrix composites offer greater flaw t
Publikováno v:
Acta Materialia. 47:4125-4129
Rapid quenching of Al-Mg alloys during superplastic deformation has revealed the presence of nano-scale cavities along many grain boundaries. They were observed only under deformation conditions where grain boundary sliding was the dominant mechanism