Kevin Field

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Yukinori YamamotoOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
M.N. GussevORNLPatvirtintas el. paštas ornl.gov
Richard HowardOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Samuel A. BriggsOregon State UniversityPatvirtintas el. paštas oregonstate.edu
Phil EdmondsonProfessor - Tritium Science & Technology, University of ManchesterPatvirtintas el. paštas manchester.ac.uk
Lance SneadMassachusetts Institute of TechnologyPatvirtintas el. paštas MIT.edu
Kenneth LittrellOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Kumar SridharanUniversity of Wisconsin, MadisonPatvirtintas el. paštas wisc.edu
Dane MorganUniversity of Wisconsin, Materials SciencePatvirtintas el. paštas wisc.edu
Todd AllenUniversity of MichiganPatvirtintas el. paštas umich.edu
Bruce A. PintConsultant, retired Oak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Xunxiang HuProfessor, Sichuan UniversityPatvirtintas el. paštas scu.edu.cn
Chad M. ParishSenior Research and Development Staff, Oak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Yann Le PapeOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Caleb MasseyOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Dalong ZhangAssociate Professor of Mechanical Engineering, Baylor UniversityPatvirtintas el. paštas baylor.edu
Niyanth SridharanLincoln Electric CompanyPatvirtintas el. paštas lincolnelectric.in
Gary S WasMITPatvirtintas el. paštas mit.edu
Lizhen TanOak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov
Yutai KatohMaterials Science and Technology Division, Oak Ridge National LaboratoryPatvirtintas el. paštas ornl.gov

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Kevin Field

University of Michigan

Patvirtintas el. paštas umich.edu - Pagrindinis puslapis

Nuclear Materials Materials Science Characterization


Pavadinimas Rūšiuoti pagal šaltinius Rūšiuoti pagal metus Rūšiuoti pagal pavadinimą	Cituota Cituota	Metai
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Y Yamamoto, BA Pint, KA Terrani, KG Field, Y Yang, LL Snead Journal of Nuclear Materials 467, 703-716, 2015	538	2015
Radiation Tolerance of Neutron-Irradiated Model Fe-Cr-Al Alloys KG Field, X Hu, KC Littrell, Y Yamamoto, LL Snead Journal of Nuclear Materials 465, 746-755, 2015	332	2015
Radiation effects in concrete for nuclear power plants – Part I: Quantification of radiation exposure and radiation effects KG Field, I Remec, Y Le Pape Nuclear Engineering and Design 282, 126-143, 2015	254	2015
Irradiation-enhanced α′ precipitation in model FeCrAl alloys PD Edmondson, SA Briggs, Y Yamamoto, RH Howard, K Sridharan, ... Scripta Materialia 116, 112-116, 2016	193	2016
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys SA Briggs, PD Edmondson, KC Littrell, Y Yamamoto, RH Howard, ... Acta Materialia 129, 217-228, 2017	176	2017
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys KG Field, SA Briggs, K Sridharan, RH Howard, Y Yamamoto Journal of Nuclear Materials 489, 118-128, 2017	161	2017
Automated defect analysis in electron microscopic images W Li, KG Field, D Morgan npj Computational Materials 4 (1), 36, 2018	150	2018
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys CM Parish, KG Field, AG Certain, JP Wharry Journal of Materials Research 30 (9), 2015	139	2015
Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys JC Haley, SA Briggs, PD Edmondson, K Sridharan, SG Roberts, ... Acta Materialia 136, 390-401, 2017	134	2017
Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys MN Gussev, KG Field, Y Yamamoto Materials & Design 129, 227-238, 2017	131	2017
Handbook on the material properties of FeCrAl alloys for nuclear power production applications KG Field, MA Snead, Y Yamamoto, KA Terrani Nuclear Technology Research and Development, 2017	120	2017
Radiation effects in concrete for nuclear power plants, Part II: Perspective from micromechanical modeling Y Le Pape, K Field, I Remec Nuclear Engineering and Design 282, 144-157, 2015	114	2015
Deformation Behavior of Laser Welds in High Temperature Oxidation Resistant Fe-Cr-Al Alloys for Fuel Cladding Applications KG Field, MN Gussev, Y Yamamoto, LL Snead Journal of Nuclear Materials 454 (1-3), 352-358, 2014	97	2014
Response of nanoclusters in a 9Cr ODS steel to 1 dpa, 525 C proton irradiation AG Certain, KG Field, TR Allen, MK Miller, J Bentley, JT Busby Journal of nuclear materials 407 (1), 2-9, 2010	88	2010
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel KG Field, LM Barnard, CM Parish, JT Busby, D Morgan, TR Allen Journal of Nuclear Materials 435 (1-3), 172-180, 2012	86	2012
Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels MN Gussev, KG Field, JT Busby Journal of Nuclear Materials 460, 139-152, 2015	83	2015
Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing MN Gussev, RH Howard, KA Terrani, KG Field Nuclear Engineering and Design 320, 298-308, 2017	81	2017
Role of Scale Factor During Tensile Testing of Small Specimens MN Gussev, JT Busby, KG Field, MA Sokolov, SE Gray Small Specimen Test Techniques 6, 1-19, 2014	80	2014
Microstructure evolution of T91 irradiated in the BOR60 fast reactor Z Jiao, S Taller, K Field, G Yeli, MP Moody, GS Was Journal of Nuclear Materials 504, 122-134, 2018	79	2018
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding SS Raiman, KG Field, RB Rebak, Y Yamamoto, KA Terrani Journal of Nuclear Materials 536, 152221, 2020	75	2020

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