受强制性开放获取政策约束的文章 - Gary S Was了解详情
无法在其他位置公开访问的文章：22 篇
Materials for future nuclear energy systems
GS Was, D Petti, S Ukai, S Zinkle
Journal of Nuclear Materials 527, 151837, 2019
强制性开放获取政策： US Department of Energy
Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
E Getto, K Sun, AM Monterrosa, Z Jiao, MJ Hackett, GS Was
Journal of Nuclear Materials 480, 159-176, 2016
强制性开放获取政策： US National Science Foundation
Oxide growth and dissolution on 316L stainless steel during irradiation in high temperature water
RD Hanbury, GS Was
Corrosion Science 157, 305-311, 2019
强制性开放获取政策： US National Science Foundation
Quantitative analysis of localized stresses in irradiated stainless steels using high resolution electron backscatter diffraction and molecular dynamics modeling
DC Johnson, B Kuhr, D Farkas, GS Was
Scripta Materialia 116, 87-90, 2016
强制性开放获取政策： US Department of Energy
Methodology for determining void swelling at very high damage under ion irradiation
E Getto, K Sun, S Taller, AM Monterrosa, Z Jiao, GS Was
Journal of Nuclear Materials 477, 273-279, 2016
强制性开放获取政策： US National Science Foundation
Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials
LN Clowers, Z Jiao, GS Was
Journal of Nuclear Materials 565, 153722, 2022
强制性开放获取政策： US Department of Energy
Stress localization resulting from grain boundary dislocation interactions in relaxed and defective grain boundaries
B Kuhr, D Farkas, IM Robertson, D Johnson, G Was
Metallurgical and Materials Transactions A 51, 667-683, 2020
强制性开放获取政策： US Department of Energy
Stress corrosion cracking of ferritic-martensitic steels in simulated boiling water reactor environment
PM Ahmedabadi, GS Was
Corrosion 72 (1), 66-77, 2016
强制性开放获取政策： US Department of Energy
Atomistic simulation of the obstacle strengths of radiation-induced defects in an Fe–Ni–Cr austenitic stainless steel
J Hesterberg, R Smith, GS Was
Modelling and Simulation in Materials Science and Engineering 27 (8), 085004, 2019
强制性开放获取政策： US Department of Energy
Insights into the roles of intergranular carbides in the initiation of intergranular stress corrosion cracking of alloy 690 in simulated PWR primary water
W Kuang, X Feng, H Yue, GS Was, X Hao
Corrosion Science 196, 110048, 2022
强制性开放获取政策： 国家自然科学基金委员会
Micromechanistic origin of irradiation-assisted stress corrosion cracking
B Cui, MD McMurtrey, GS Was, IM Robertson
Philosophical Magazine 94 (36), 4197-4218, 2014
强制性开放获取政策： US Department of Energy
Role of slip behavior in the irradiation assisted stress corrosion cracking in austenitic steels
MD McMurtrey, GS Was
Proceedings of the 15th International Conference on Environmental …, 2016
强制性开放获取政策： US Department of Energy
The key factors affecting crack growth behavior of neutron-irradiated austenitic alloys
Y Ashida, A Flick, PL Andresen, GS Was
Proceedings of the 15th International Conference on Environmental …, 2016
强制性开放获取政策： US Department of Energy
Developing Waste Forms for Transuranic Elements: Quaternary Neptunium Fluorides of the Type NaxMNp6F30 (M = Ti, V, Cr, Mn, Fe, Co, Ni, Al, Ga)
TK Deason, G Morrison, A Mofrad, HB Tisdale, J Amoroso, D DiPrete, ...
Journal of the American Chemical Society 145 (1), 465-475, 2022
强制性开放获取政策： US National Science Foundation, US Department of Energy
Stress Corrosion Crack Initiation Susceptibility of Irradiated Austenitic Stainless Steels
KJ Stephenson, Y Ashida, JT Busby, GS Was
Proceedings of the 15th International Conference on Environmental …, 2016
强制性开放获取政策： US Department of Energy
Grain boundary oxidation and stress corrosion cracking in nickel-base alloys strained in supercritical water
T Moss, MJ Olszta, W Grant, GS Was
Proceedings of the 15th International Conference on Environmental …, 2016
强制性开放获取政策： US Department of Energy
Novel technique for quantitative measurement of localized stresses near dislocation channel—Grain boundary interaction sites in irradiated stainless steel
DC Johnson, GS Was
Proceedings of the 18th International Conference on Environmental …, 2019
强制性开放获取政策： US Department of Energy
IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing
JR Hesterberg, Z Jiao, GS Was
Proceedings of the 18th International Conference on Environmental …, 2019
强制性开放获取政策： US Department of Energy
Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts
J Michalička, Z Jiao, G Was
Proceedings of the 18th International Conference on Environmental …, 2019
强制性开放获取政策： US Department of Energy
Plastic deformation processes accompanying stress corrosion crack propagation in irradiated austenitic steels
MN Gussev, GS Was, JT Busby, KJ Leonard
Proceedings of the 18th International Conference on Environmental …, 2019
强制性开放获取政策： US Department of Energy
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