Ben Maier

Profile Information
Name
Dr. Ben Maier
Institution
Westinghouse Electric Company
Position
Principal Engineer
h-Index
ORCID
0000-0003-0304-9128
Publications:
"A Novel Approach for Manufacturing Oxide Dispersion Strengthened (ODS) Steel Cladding Tubes using Cold Spray Technology" Ben Maier, Mia Lenling, Stuart Maloy, Kumar Sridharan, Nuclear Engineering and Technology Vol. 2019 Link
A novel fabrication method of oxide dispersion strengthened (ODS) steel cladding tubes for advanced fast reactors has been investigated using the cold spray powder-based materials deposition process. Cold spraying has the potential advantage for rapidly fabricating ODS cladding tubes in comparison with the conventional multi-step extrusion process. A gas atomized spherical 14YWT (Fe-14%Cr, 3%W, 0.4%Ti, 0.2%Y, 0.01%O) powder was sprayed on a rotating cylindrical 6061-T6 aluminum mandrel using nitrogen as the propellant gas. The powder lacked the oxygen content needed to precipitate the nanoclusters in ODS steel, therefore this work was intended to serve as a proof-of-concept study to demonstrate that free-standing steel cladding tubes with prototypical ODS composition could be manufactured using the cold spray process. The spray process produced an approximately one-millimeter thick, dense 14YWT deposit on the aluminum-alloy tube. After surface polishing of the 14YWT deposit to obtain desired cladding thickness and surface roughness, the aluminum-alloy mandrel was dissolved in an alkaline medium to leave behind a free-standing ODS tube. The as-fabricated cladding tube was annealed at 1000 °C for 1 hour in an argon atmosphere to improve the overall mechanical properties of the cladding.
Presentations:
"Cold Spray Coatings for Accident Tolerant Zr-Alloy Cladding in Light Water Reactors" Hwasung Yeom, Ben Maier, Peng Xu, Kumar Sridharan, ANS Annual Meeting 2018 June 18-22, (2018)
"Manufacturing of nanostructured ODS steel cladding tubes for advanced nuclear reactors using cold spray technology" Mia Lenling, Hwasung Yeom, Ben Maier, Greg Johnson, David Hoelzer, Peter Hosemann, Stuart Maloy, Kumar Sridharan, Jeffrey Graham, The Minerals, Metals and Materials Society (TMS) 2019 March 10-14, (2019)
NSUF Articles:
U.S. DOE Nuclear Science User Facilities Awards 35 Rapid Turnaround Experiment Research Proposals - Awards total approximately $1.3 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Wednesday, September 20, 2017 - Calls and Awards
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.2 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, June 18, 2018 - Calls and Awards
Additional Publications:
"Enhancing Crack Detection in Critical Structures Using Machine Learning and 3D Digital Image Correlation" D.C. Roache, M.C Price, J. L.Walters, B.R Maier, X. Li, O. Holzmond, [2024] Experimental Mechanics · DOI: 10.1007/s11340-024-01098-2
"Unveiling fracture mechanics of a curved coating/substrate system by combined digital image correlation and numerical finite element analyses" Timothy M. Harrell, Clifton H. Bumgardner, David C. Roache, Jorie L. Walters, Benjamin R. Maier, Edward J. Lahoda, Xiaodong Li, Diana E. Burden, [2024] Engineering Fracture Mechanics · DOI: 10.1016/j.engfracmech.2023.109827
"High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer" Greg Johnson, Benjamin Maier, Tyler Dabney, Kumar Sridharan, Hwasung Yeom, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154822
"In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials" J. Paul Forna-Kreutzer, Jon Ell, Harold Barnard, Benjamin R. Maier, Edward Lahoda, Jorie Walters, Robert O. Ritchie, Dong Liu, Guanjie Yuan, [2023] Materials & Design · DOI: 10.1016/j.matdes.2023.112373
"Effects of Cold Spray Chromium Coatings on the Properties of Zirconium Alloys" Javier E. Romero, Andrew J. Mueller, Benjamin R. Maier, Jonna M. Partezana, John L. Lyons, William A. Byers, Guoqiang Wang, Arash Parsi, Richard S. Stiteler, Magnus Limbäck, Jorie L. Walters, [2021] · DOI: 10.1520/stp162220190065

Following the Fukushima accident in 2011, the nuclear industry has focused significant research efforts on the development of fuels that are more tolerant to a temporary loss of active cooling than are current designs. This requires the development of cladding materials that can withstand aqueous environments in excess of 1473 K, while avoiding the strong exothermic oxidation reaction that zirconium alloys undergo in those conditions. This has to be accomplished while maintaining or improving cladding performance during normal operating conditions. For this purpose, chromium coatings have been applied using cold spray to cladding tubes made of current standard zirconium alloys. Cold spray is a low-temperature process that allows deposition of metallic layers at room temperature and ambient conditions, by propelling powder particles at supersonic velocities directly onto the surface of substrates using pressurized gas. This paper discusses metallurgical phenomena observed during the development and testing of cold spray chromium coatings on zirconium alloys. Parameters of the solid-state cold spray process have been optimized to minimize the deformation induced on the zirconium substrate, while producing dense and adherent coatings. Coated tubes have been subjected to extensive testing including corrosion in aqueous environments and mechanical testing in a range of temperatures between room temperature and 1673 K. Phenomena observed include the effect of chromium on the electrochemical corrosion potential of the system, which is critical to simulate and predict the in-reactor corrosion and crud deposition under pressurized water reactor water chemistry conditions. Interdiffusion between chromium and zirconium at high temperatures in an oxidative environment, leading to the appearance of chromium precipitates or the formation of eutectics and melting when the temperatures exceed 1573 K, is also discussed. Finally, the effect of in-reactor conditions on the chromium-zirconium system is presented from characterization of samples irradiated at the Massachusetts Institute of Technology Reactor.

"Radiation response of FeCrAl-coated Zircaloy-4" Hyosim Kim, Jonathan G. Gigax, Tianyao Wang, Benjamin R. Maier, Hwasung Yeom, Greg O. Johnson, Tyler Dabney, Kumar Sridharan, Kenneth L. Peddicord, Lin Shao, Miltiadis Kennas, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152175 · EID: 2-s2.0-85084707302 · ISSN: 0022-3115
"Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission" Alex Jarama, Clifton H. Bumgardner, Frederick M. Heim, Jorie Walters, Javier Romero, Benjamin Maier, Xiaodong Li, David C. Roache, [2020] Materials Science and Engineering A · DOI: 10.1016/j.msea.2019.138850 · EID: 2-s2.0-85077362623 · ISSN: 0921-5093
"Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding" Miltiadis Kennas, Hyosim Kim, Tianyao Wang, Benjamin R. Maier, Hwasung Yeom, Greg O. Johnson, Kumar Sridharan, Lin Shao, Jonathan G. Gigax, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.05.021
"Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding" Miltiadis Kennas, Hyosim Kim, Tianyao Wang, Benjamin R. Maier, Hwasung Yeom, Greg O. Johnson, Kumar Sridharan, Lin Shao, Jonathan G. Gigax, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.05.021 · EID: 2-s2.0-85066234963 · ISSN: 0022-3115
"A novel approach for manufacturing oxide dispersion strengthened (ODS) steel cladding tubes using cold spray technology" Mia Lenling, Hwasung Yeom, Greg Johnson, Stuart Maloy, Kumar Sridharan, Benjamin Maier, [2019] Nuclear Engineering and Technology · DOI: 10.1016/j.net.2019.01.015
"Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding" Hwasung Yeom, Greg Johnson, Tyler Dabney, Jorie Walters, Peng Xu, Javier Romero, Hemant Shah, Kumar Sridharan, Benjamin Maier, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.03.039
"Interface reactions and mechanical properties of FeCrAl-coated Zircaloy-4" Miltiadis Kennas, Hyosim Kim, Benjamin R. Maier, Hwasung Yeom, Greg O. Johnson, Kumar Sridharan, Lin Shao, Jonathan G. Gigax, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.03.004
"Development of cold spray FeCrAl coatings for accident tolerant fuel" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092187328 · ISSN: 0003-018X
"Development of cold spray process for manufacturing of oxide dispersion strengthened (ODS) steel cladding tubes" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092158322 · ISSN: 0003-018X
"Development of cold-sprayed chromium coatings for accident tolerant fuel cladding" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092187967 · ISSN: 0003-018X
"Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding" Greg Johnson, Hwasung Yeom, Ben Maier, Jorie Walters, Kumar Sridharan, Tyler Dabney, [2019] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2019.100715 · EID: 2-s2.0-85075300770 · ISSN: 2352-1791
"High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments" Benjamin Maier, Greg Johnson, Tyler Dabney, Mia Lenling, Kumar Sridharan, Hwasung Yeom, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151737 · EID: 2-s2.0-85070079154 · ISSN: 0022-3115
"Improving deposition efficiency in cold spraying chromium coatings by powder annealing" Tyler Dabney, Greg Johnson, Benjamin Maier, Mia Lenling, Kumar Sridharan, Hwasung Yeom, [2019] International Journal of Advanced Manufacturing Technology · DOI: 10.1007/s00170-018-2784-1 · EID: 2-s2.0-85054471693 · ISSN: 1433-3015
"Manufacturing Oxide Dispersion-Strengthened (ODS) Steel Fuel Cladding Tubes Using the Cold Spray Process" Hwasung Yeom, Benjamin Maier, Greg Johnson, Tyler Dabney, Jeffrey Graham, Peter Hosemann, David Hoelzer, Stuart Maloy, Kumar Sridharan, Mia Lenling, [2019] JOM · DOI: 10.1007/s11837-019-03582-w · EID: 2-s2.0-85067392001 · ISSN: 1543-1851
"Oxidation of cold spray cr coatings in high temperature steam environments" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092199447 · ISSN: 0003-018X
"In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications" Hwasung Yeom, Greg Johnson, Tyler Dabney, Jing Hu, Peter Baldo, Meimei Li, Kumar Sridharan, Benjamin R. Maier, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.10.023
"A novel approach to advanced nanostructured materials manufacturing" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062990289 · ISSN: 0003-018X
"Cold spray coatings for accident tolerant Zr-alloy cladding in light water reactors" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062983960 · ISSN: 0003-018X
"Correction to: Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors (JOM, (2018), 70, 2, (198-202), 10.1007/s11837-017-2643-9)" Hwasung Yeom, Greg Johnson, Tyler Dabney, Jorie Walters, Javier Romero, Hemant Shah, Peng Xu, Kumar Sridharan, Benjamin Maier, [2018] JOM · DOI: 10.1007/s11837-017-2678-y · EID: 2-s2.0-85035114864
"Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors" Hwasung Yeom, Greg Johnson, Tyler Dabney, Jorie Walters, Javier Romero, Hemant Shah, Peng Xu, Kumar Sridharan, Benjamin Maier, [2018] JOM · DOI: 10.1007/s11837-017-2643-9 · EID: 2-s2.0-85033595047
"Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™" Benjamin Maier, Greg Johnson, Tyler Dabney, Jorie Walters, Kumar Sridharan, Hwasung Yeom, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.05.014
"Magnetron sputter deposition of zirconium-silicide coating for mitigating high temperature oxidation of zirconium-alloy" Benjamin Maier, Robert Mariani, David Bai, Steven Fronek, Peng Xu, Kumar Sridharan, Hwasung Yeom, [2017] Surface and Coatings Technology · DOI: 10.1016/j.surfcoat.2017.03.018 · EID: 2-s2.0-85014946193
"Multi-functional zirconium-silicide coatings on zirconium-alloy for improved accident tolerance" [2017] Transactions of the American Nuclear Society · EID: 2-s2.0-85033496182
"Silver diffusivity measurement in ZrC with SIMS to study the release behavior of 110mAg for nuclear fuel applications" Young-Ki Yang, Todd R. Allen, Benjamin Maier, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.06.010 · EID: 2-s2.0-84974560060 · ISSN: 0022-3115
"Development of zirconium-silicide coatings for accident tolerant zirconium-Alloy fuel cladding" [2016] International Congress on Advances in Nuclear Power Plants, ICAPP 2016 · EID: 2-s2.0-84986272566
"Development of zirconium-silicide coatings for improved performance zirconium-Alloy fuel cladding" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85032914353
"Evolution of multilayered scale structures during high temperature oxidation of ZrSi2" Ben Maier, Robert Mariani, David Bai, Kumar Sridharan, Hwasung Yeom, [2016] Journal of Materials Research · DOI: 10.1557/jmr.2016.363 · EID: 2-s2.0-84992046680
"Surface Modification of Polycrystalline Diamond Compacts by Carbon Ion Irradiation" Lianyi Chen, Ting Chiang Lin, Benjamin R. Maier, Beata Tyburska, Kumar Sridharan, Kornel Ehmann, Xiaochun Li, Madhu S.K. Mutyala, [2016] Procedia Manufacturing · DOI: 10.1016/j.promfg.2016.08.052 · EID: 2-s2.0-85014393272
"Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding" Brenda L. Garcia-Diaz, Benjamin Hauch, Luke C. Olson, Robert L. Sindelar, Kumar Sridharan, Benjamin R. Maier, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.06.028 · EID: 2-s2.0-84956593174 · ISSN: 0022-3115
"Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries" B.R. Maier, T.R. Allen, Y. Huang, [2014] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2014.06.001 · EID: 2-s2.0-84904728847
"MAX phase coatings for accident tolerant nuclear fuel" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904634231
"Corrosion protection of 5xxx series aluminum-alloy by cold spray process" [2013] Proceedings of the International Thermal Spray Conference · EID: 2-s2.0-84907079883
"Optimal conditions for high current proton irradiations at the university of Wisconsin's ion beam laboratory" K. G. Field, T. J. Eiden, T. J. Gerczak, B. R. Maier, O. Albakri, K. Sridharan, T. R. Allen, C. J. Wetteland, [2013] AIP Conference Proceedings · DOI: 10.1063/1.4802407 · EID: 2-s2.0-84877751460
"University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis" C. J. Wetteland, G. Cao, B. R. Maier, C. Dickerson, T. J. Gerczak, C. R. Field, K. Kriewaldt, K. Sridharan, T. R. Allen, K. G. Field, [2013] AIP Conference Proceedings · DOI: 10.1063/1.4802311 · EID: 2-s2.0-84877787240
Source: ORCID/CrossRef using DOI