基本信息
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Bio
He has worked in several areas of materials science, specializing in the deformation and fracture of metals and alloys for nuclear power plant applications. He has been involved in a broad range basic and applied programs. During his early career he focused on structural materials performance in nuclear power reactor components including high-temperature properties of light-water reactor fuel cladding, methods to ameliorate environmentally-induced cracking in boiling water piping, structural integrity of steam generator tubing, and assessment of nondestructive inspection techniques for evaluating flaws in primary pressure boundary components. Presently he leads a large, multidisciplinary program to develop the scientific basis for advanced, radiation tolerant, low-activation materials for first-wall/blanket structures of fusion power plants. Dr. Kurtz directs technical activities in alloy development, performance of neutron irradiation experiments, post-irradiation evaluation of mechanical and physical properties, characterization of microstructure, and computer simulations to model and predict damage evolution.
Research Interests
Papers共 218 篇Author StatisticsCo-AuthorSimilar Experts
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Yutai Kato,Nasr Ghoniem,Jaime Marian, George Odette,Lance Snead,Jean Paul Allain,Jason Trelewicz,Brian Wirth, Bill Wiffen,Richard Kurtz,Steven Zinkle
crossref(2021)
NUCLEAR MATERIALS AND ENERGY (2021): 101092
SSRN Electronic Journal (2019)
STRUCTURAL ALLOYS FOR NUCLEAR ENERGY APPLICATIONS (2019)
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Author Statistics
#Papers: 218
#Citation: 6874
H-Index: 40
G-Index: 69
Sociability: 7
Diversity: 0
Activity: 0
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