Aditya Shivprasad

Profile Information
Name
Dr. Aditya Shivprasad
Institution
Electric Power Research Institute
Position
Senior Technical Leader
Affiliation
EPRI
h-Index
10
ORCID
0000-0001-8515-2756
Biography

Aditya Shivprasad is a Senior Technical Leader in the Nuclear Fuels team at the Electric Power Research Institute (EPRI).

Aditya joined EPRI in 2024 and works to manage and support collaborative research projects within the Fuel Reliability Program and Nuclear Fuel Industry Research program on fuel cladding corrosion, hydriding, and fuel performance issues.

Prior to joining EPRI, Aditya worked at Los Alamos National Laboratory as a Scientist. Aditya received his B.S. degree in Chemical and Nuclear Engineering from the University of California, Berkeley and earned his PhD degree in Nuclear Engineering from the Pennsylvania State University.

Expertise
Diffraction, Fuels, Hydrides, Hydrogen, Metal Hydrides, Microreactors, Moderators, Space Reactors, Synchrotron, Yttrium Hydrides (YHx), Yttrium Materials, Zircaloy, Zirconium
Additional Publications:
"Advancements in Yttrium Hydride Moderator Development" Chase Taylor, Erik Luther, Theresa Cutler, Aditya Shivprasad, J. Keith Jewell, Dasari V. Rao, Michael Davenport, Holly Trellue, [2022] Nuclear Technology · DOI: 10.1080/00295450.2022.2043088 · EID: 2-s2.0-85129168909 · ISSN: 1943-7471
"The u3si2-H system" V. Kocevski, T.L. Ulrich, J.R. Wermer, D.A. Andersson, J.T. White, A.P. Shivprasad, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153278 · EID: 2-s2.0-85116946820 · ISSN: 0022-3115
"A density functional theory and neutron diffraction study of the ambient condition properties of sub-stoichiometric yttrium hydride" Sven C. Vogel, Aditya P. Shivprasad, Erik P. Luther, David A. Andersson, Dasari V. Rao, Dan Kotlyar, Bjørn Clausen, Michael W.D. Cooper, Vedant K. Mehta, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152837 · EID: 2-s2.0-85100390898 · ISSN: 0022-3115
"Materials for Small Nuclear Reactors and Micro Reactors, Including Space Reactors" Marisa J. Monreal, Aditya P. Shivprasad, Sven C. Vogel, [2021] JOM · DOI: 10.1007/s11837-021-04897-3 · EID: 2-s2.0-85115409190 · ISSN: 1543-1851
"Thermophysical properties of high-density, sintered monoliths of yttrium dihydride in the range 373–773 K" S.C. Vogel, V.K. Mehta, M.W.D. Cooper, T.A. Saleh, J.T. White, J.R. Wermer, E.P. Luther, H.R. Trellue, A.P. Shivprasad, [2021] Journal of Alloys and Compounds · DOI: 10.1016/j.jallcom.2020.156303 · EID: 2-s2.0-85089947297 · ISSN: 0925-8388
"Elastic moduli of high-density, sintered monoliths of yttrium dihydride" D.M. Frazer, V.K. Mehta, M.W.D. Cooper, T.A. Saleh, J.T. White, J.R. Wermer, E.P. Luther, D.V. Rao, A.P. Shivprasad, [2020] Journal of Alloys and Compounds · DOI: 10.1016/j.jallcom.2020.153955 · EID: 2-s2.0-85079145672 · ISSN: 0925-8388
"Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering" J.T. White, D.D. Byler, D.M. Frazer, A.P. Shivprasad, T.A. Saleh, B. Gong, T. Yao, J. Lian, K.J. McClellan, E. Kardoulaki, [2020] Journal of Alloys and Compounds · DOI: 10.1016/j.jallcom.2019.153216 · EID: 2-s2.0-85076825057 · ISSN: 0925-8388
"Microbeam X-Ray Absorption Near-Edge Spectroscopy of Alloying Elements in the Oxide Layers of Irradiated Zircaloy-2" Arthur T. Motta, Aylin Kucuk, Suresh Yagnik, Zhonghou Cai, Aditya P. Shivprasad, [2018] Zirconium in the Nuclear Industry: 18th International Symposium · DOI: 10.1520/stp159720160076

Hydrogen pickup of zirconium-based fuel cladding and structural materials during in-reactor corrosion can degrade fuel components because the ingress of hydrogen can lead to the formation of brittle hydrides. In the boiling water reactor (BWR) environment, Zircaloy-2 fuel cladding and structural components such as water rods and channels can experience accelerated hydrogen pickup, whereas Zircaloy-4 components exposed to similar conditions do not. Because the principal difference between the two alloys is that Zircaloy-2 contains nickel, accelerated hydrogen pickup has been hypothesized to result from the presence of nickel. However, an understanding of the mechanism by which this acceleration occurs is still lacking. We investigated the link between hydrogen pickup and the oxidation behavior of alloying elements when incorporated into the oxide layers formed on zirconium alloys when corroded in the reactor. Synchrotron radiation microbeam X-ray absorption near-edge spectroscopy (XANES) at the Advanced Photon Source was performed on carefully selected BWR-corroded Zircaloy-2 water rods at an assembly-averaged burnup ranging from 32.8 to 74.6 GWd/MTU to determine the oxidation states of alloying elements, such as iron and nickel, within the oxide layers as a function of distance from the oxide-metal interface at high burnup. Samples were chosen for comparison based on having similar oxide thicknesses, processing, elevation, reactors, and fluences but different hydrogen pickup fractions. Examinations of the oxide layers formed on these samples showed that (1) the oxidation states of these alloying elements changed with distance from the oxide-metal interface, (2) these elements exhibited delayed oxidation relative to the host zirconium, and (3) nickel in Zircaloy-2 remained metallic in the oxide layer at a longer distance from the oxide-metal interface than iron. An analysis of these results showed an apparent correlation between the delayed oxidation of nickel and higher hydrogen pickup of Zircaloy-2 at high burnup.

"Essential aspects of controlling the oxygen content of molten tin in engineering applications" Aditya Prahlad Shivprasad, David Frazer, Peter Hosemann, Alan Michael Bolind, [2013] Materials and Design · DOI: 10.1016/j.matdes.2013.04.096 · EID: 2-s2.0-84879242230
"Gamma-ray energies in the decay of 38Cl" M.L. Keck, E.B. Norman, A.P. Shivprasad, K.S. Krane, [2012] Applied Radiation and Isotopes · DOI: 10.1016/j.apradiso.2011.12.033 · EID: 2-s2.0-84857137994
Source: ORCID/CrossRef using DOI