Todd Allen

Transport Mechanism and Microstructural Effects on Ag and Cs Diffusion in beta-SiC

Lead Institution

University of Wisconsin, Madison

Principal Investigator

Todd Allen

Project type

Exploratory Research

The Very High Temperature Reactor (VHTR) has been identified by the Generation IV initiative and by the US Department of Energy's Next Generation Nuclear Plant (NGNP) as a promising future…

Microstructural and Irradiation Effects on Ag and Cs Diffusion in CVD-SiC

Lead Institution

University of Wisconsin, Madison

Principal Investigator

Todd Allen

Project type

Large-Scale EMSL Research

The DOE has selected the Very High Temperature Gas Cooled Reactor (VHTR) as its next generation nuclear plant. The VHTR is designed to operate at higher temperatures than conventional light water…

SIMS and AES/SAM for Interfacial Characterization of Oxide Multilayers

Lead Institution

University of Wisconsin, Madison

Principal Investigator

Todd Allen

Project type

Large-Scale EMSL Research

Corrosion resistance of candidate materials is a critical concern for their application to Generation IV nuclear systems. The corrosion behavior of Incoloy alloy 800H, ferritic-martensitic steel…

Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor

Lead Institution

Idaho National Laboratory

Principal Investigator

Jian Gan

Project type

Exploratory Research

Objective__To evaluate the radiation response of different alloy system for the microstructural and microchemical analysis. Approach__Using Ni-ion irradiation at T=500C to doses up to 150 dpa for…

Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor

Lead Institution

Idaho National Laboratory

Principal Investigator

Jian Gan

Project type

Exploratory Research

Objective__To evaluate the radiation response of different alloy system for the microstructural and microchemical analysis. Approach__Using Ni-ion irradiation at T=500C to doses up to 150 dpa for…

FIB/SEM/EBSD/EDS Study of the Grain boundary Character Effect on Precipitation

Lead Institution

University of Wisconsin, Madison

Principal Investigator

Todd Allen

Project type

Capability Research

INCOLOY Alloy 800H is a candidate material for the Next Generation Nuclear Plant. Its grain boundary character distribution has been found to be effectively adjusted by means of grain boundary…

EMSL Science Overview

Todd Allen

Projects

Transport Mechanism and Microstructural Effects on Ag and Cs Diffusion in beta-SiC

Microstructural and Irradiation Effects on Ag and Cs Diffusion in CVD-SiC

SIMS and AES/SAM for Interfacial Characterization of Oxide Multilayers

Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor

Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor

FIB/SEM/EBSD/EDS Study of the Grain boundary Character Effect on Precipitation