|"Advanced synchrotron characterization techniques for fusion materials science" David Sprouster, J Trelewicz, Lance Snead, Daniel Morrall, Takaaki Koyanagi, X Hu, Chad Parish, Lizhen Tan, Yutai Katoh, Brian Wirth, Journal of Nuclear Materials Vol. 543 2020 152574 Link|
"Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature"
Todd Allen, Zhijie Jiao, Djamel Kaoumi, Janelle Wharry, cem topbasi, Aaron Kohnert, Leland Barnard, Alicia Certain, Kevin Field, Gary Was, Dane Morgan, Arthur Motta, Brian Wirth, Yong Yang,
Journal of Materials Research
Designing materials for performance in high-radiation fields can be accelerated through a carefully chosen combination of advanced multiscale modeling paired with appropriate experimental validation. The studies reported in this work, the combined efforts of six universities working together as the Consortium on Cladding and Structural Materials, use that approach to focus on improving the scientific basis for the response of ferritic–martensitic steels to irradiation. A combination of modern modeling techniques with controlled experimentation has specifically focused on improving the understanding of radiation-induced segregation, precipitate formation and growth under radiation, the stability of oxide nanoclusters, and the development of dislocation networks under radiation. Experimental studies use both model and commercial alloys, irradiated with both ion beams and neutrons. Transmission electron microscopy and atom probe are combined with both first-principles and rate theory approaches to advance the understanding of ferritic–martensitic steels.
"Predicting neutron damage using TEM with in situ ion irradiation and computer modeling"
Brian Wirth, Donghua Xu, Marquis Kirk, Meimei Li,
Journal of Nuclear Materials
We have constructed a computer model of irradiation defect production closely coordinated with TEM and in situ ion irradiation of Molybdenum at 80 °C over a range of dose, dose rate and foil thickness. We have reexamined our previous ion irradiation data to assign appropriate error and uncertainty based on more recent work. The spatially dependent cascade cluster dynamics model is updated with recent Molecular Dynamics results for cascades in Mo. After a careful assignment of both ion and neutron irradiation dose values in dpa, TEM data are compared for both ion and neutron irradiated Mo from the same source material. Using the computer model of defect formation and evolution based on the in situ ion irradiation of thin foils, the defect microstructure, consisting of densities and sizes of dislocation loops, is predicted for neutron irradiation of bulk material at 80 °C and compared with experiment. Reasonable agreement between model prediction and experimental data demonstrates a promising direction in understanding and predicting neutron damage using a closely coordinated program of in situ ion irradiation experiment and computer simulation.
|"Multiscale modeling of fission gas bubble evolution in UO2 under nominal operating conditions" Brian Wirth, NUMAT 2018 October 15-18, (2018)|
This NSUF Profile is 50
Authored an NSUF-supported publication
Presented an NSUF-supported publication
Submitted an RTE Proposal to NSUF
Awarded an RTE Proposal
Collaborated on 3+ RTE Proposals
Characterization of the Microstructures and Mechanical Properties of Advanced Structural Alloys for Radiation Service: A Comprehensive Library of ATR Irradiated Alloys and Specimen - FY 2008 Call for User Proposals, #139
High Fluence Embrittlement Database and ATR Irradiation Facility for LWR Vessel Life Extension - FY 2009 Fall Solicitation for User Proposals, #153
Ion Irradiation for High Fidelity Simulation of High Dose Neutron Irradiation - FY 2019 RTE 1st Call, #1541
Microstructure Analysis of HIgh Dose Neutron Irradiated Microstructures - FY 2013 RTE Solicitation, #425
Microstructure Analysis of High Dose Neutron Irradiated Microstructures - FY 2016 RTE 1st Call, #604