Sam Bell

Profile Information
Name
Dr. Sam Bell
Institution
Oak Ridge National Laboratory
Position
Research Associate
Affiliation
ANS, TMS, AMPP, ASM
h-Index
11
ORCID
0000-0002-5190-5657
Biography

Sam Bell is a nuclear materials scientist with five years of experience evaluating reactor materials in extreme environments at a national laboratory. Competencies include creep and fatigue behavior, fuel system performance, reactor safety, material degradation, high temperature material compatibility, aqueous corrosion, and mechanical testing/evaluation. He completed his Ph.D. under Dr. Steven Zinkle at the University of Tennessee, Knoxville while working at in the Corrosion Science and Technology group at Oak Ridge National Laboratory. After graduating, he was brought on as a research associate into the same group where he is continuing to explore material mechanical performance and chemical compatibility under extreme environments. Current research interests include fuel system response to accident and off-normal scenarios, particularly the thermomechanical response of cladding materials to transient heating and dynamic loading. Other interests include novel use of modern in-situ strain techniques to better understand the relationship between microstructure and performance for additively manufactured components.

Expertise
Corrosion, Mechanical Performance, Thermophysical
Additional Publications:
"Recrystallization driven softening and heating rate dependencies of FeCrAl nuclear fuel cladding during accident transients" M.J. Ridley, N.A. Capps, R.T. Sweet, Y. Yamamoto, C.P. Massey, S.B. Bell, [2025] Materialia · DOI: 10.1016/j.mtla.2025.102432
"Step-loaded creep testing of Zircaloy-4 cladding at higher temperatures in the α-phase" M.J. Ridley, C.P. Massey, N.A. Capps, S.B. Bell, [2025] Acta Materialia · DOI: 10.1016/j.actamat.2025.120821
"In-situ strain behavior and BISON simulations of Zircaloy cladding subjected to temperature cycling separate-effects tests in a steam environment" Nathan A. Capps, Mackenzie J. Ridley, Sam B. Bell, Nicholas R. Brown, Jennifer I. Espersen, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155570
"Wrought FeCrAl alloy (C26M) cladding behavior and burst under simulated loss-of-coolant accident conditions" C.P. Massey, J.A. Hirschhorn, S.B. Bell, K.A. Kane, R.T. Sweet, [2025] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2024.113712
"In-situ determination of strain during transient burst testing and the temperature dependence of Zircaloy-4 claddings" K.A. Kane, M.J. Ridley, B.E. Garrison, B.S. Johnston, N.A. Capps, S.B. Bell, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.154910
"BISON validation to in situ cladding burst test and high-burnup LOCA experiments" M. Ridley, Y. Yan, S. Bell, K. Kane, N. Capps, [2023] Annals of Nuclear Energy · DOI: 10.1016/j.anucene.2023.109905
"Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method" S. Bell, B. Garrison, M. Ridley, M. Gussev, K. Linton, N. Capps, K. Kane, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.154063
"Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing" T. Graening, A. Evans, P. Kelly, B.A. Pint, K.A. Kane, S.B. Bell, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153679 · ISSN: 0022-3115
"Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions" S.K. Lee, S.B. Bell, N.R. Brown, B.A. Pint, K.A. Kane, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152256 · EID: 2-s2.0-85087502493 · ISSN: 0022-3115
Source: ORCID/CrossRef using DOI