Zobrazeno 1 - 10
of 256
pro vyhledávání: '"S.M. Bruemmer"'
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
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
Autor:
P.L Andreson, Jian Gan, S.M. Bruemmer, A Jensson, Todd R. Allen, Gary S. Was, Edward A. Kenik, A.D Edwards, P.M Scott, J. T. Busby
Publikováno v:
Journal of Nuclear Materials. 300:198-216
This paper presents the results of the irradiation, characterization and irradiation assisted stress corrosion cracking (IASCC) behavior of proton- and neutron-irradiated samples of 304SS and 316SS from the same heats. The objective of the study was
Autor:
S.M. Bruemmer, V.Y. Gertsman
Publikováno v:
Acta Materialia. 49:1589-1598
Samples of austenitic stainless alloys were examined by means of scanning and transmission electron microscopy. Misorientations were measured by electron backscattered diffraction. Grain boundary distributions were analyzed with special emphasis on t
Publikováno v:
Materials Science Forum. :93-98
Tensile specimens of an Al-4Mg-0.3Sc alloy in the peak-aged (8 hours at 553 K) and the over-aged (96 hours at 623 K) conditions, cold-rolled to a 70% reduction, exhibited dynamic continuous recrystallization during superplastic testing at 733 K and a
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
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_________::df65b84e5f5b19914c4e353e11164a3b
https://doi.org/10.1002/9781118787618.ch113
https://doi.org/10.1002/9781118787618.ch113
Autor:
Jian Gan, Edward A. Kenik, Jeremy T Busby, M. Daniels, S.M. Bruemmer, Danny J. Edwards, Gary S. Was
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_________::879b8ca6b0a883a3d43a87ee58638e4a
https://doi.org/10.1002/9781118787618.ch114
https://doi.org/10.1002/9781118787618.ch114
Autor:
S.M. Bruemmer, L.E. Thomas
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_________::c07224eecf3cbf4ac8447eb35f59b698
https://doi.org/10.1002/9781118787618.ch4
https://doi.org/10.1002/9781118787618.ch4