Cole A Gentry

Cole A Gentry

Computational Nuclear Engineer

Bio

Dr. Cole A. Gentry is a Computational Nuclear Engineer at Oak Ridge National Laboratory (ORNL) in the Reactor and Nuclear Systems Division. His current work focuses primarily on the development and testing of Light Water Reactor (LWR) and advanced reactor simulation capabilities in both the CASL core simulator VERA and the SCALE lattice physics code POLARIS.

Prior to joining ORNL, Dr. Gentry graduated from the University of Tennessee with a B.S. in Nuclear Engineering and worked as a Reactor Engineer at the Sequoyah Nuclear Facility for two years before returning to the University of Tennessee to earn his M.S. and Ph.D. in Nuclear Engineering. His graduate work consisted of analysis of Fully Ceramic Micro-Encapsulated (FCM) Light Water Reactor (LWR) fuel for deep burnup applications, as well as adaptation of the traditional LWR Two-Step procedure to a plate fueled Advanced High Temperature Reactor (AHTR).

Awards

  • Outstanding Masters Student 2013
  • Innovations in Fuel Cycle Research Award for the paper titled "Application of Fully Ceramic Micro-Encapsulated Fuel for Transuranic Waste Recycling in PWRs" (2012).
  • Top Collegiate Scholar Award 2008
  • Outstanding Undergraduate Awards 2003-2004, 2004-2005, 2005-2006

Projects

CASL MPACT testing and development
SCALE POLARIS testing and development

Publications

Journal Publications 

  1. C. Gentry, I. Maldonado, K. Kim. “Two-Step Procedure for Liquid Salt Cooled Reactor Analysis,” Nuclear Technology. (2018)
  2. G. Davidson, T. Pandya, S. Johnson, T. Evans, A. Isotalo, C. Gentry, W. Wieselquist. “Nuclide Depletion Capabilities in the Shift Monte Carlo Code,” Annals of Nuclear Energy, 114 pp. 259-276 (2018).
  3. C. Gentry, I. Maldonado, O. Chvala, B. Petrociv. “Neutronic Evaluation of a Liquid Salt-Cooled Reactor Assembly,” Nuclear Science and Engineering, 187 pp.166-184 (2017).
  4. N. Brown, B. Betzler, J. Carbajo, A. Wysocki, M. Greenwood, C. Gentry, A. Qualls. “Preconceptual Design of a Fluoride High Temperature Salt-Cooled Engineering Demonstration Reactor: Core Design and Safety Analysis,” Annals of Nuclear Energy, 103 pp.49-59 (2017).
  5. C. Gentry, I. Maldonado, A. Godfrey, K. Terrani, J. Gehin,  J. Powers.  “A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs,” Nuclear Technology186 pp.60-75 (2014).

Refereed Conference Proceedings

  1. C. Gentry, M. Jessee, K. Kim. “Improvements in the Polaris Implementation of the Embedded Self-Shielding Method,” Proc. PHYSOR 2018, Cancun, Mexico (April 22-26, 2018).
  2. K. Kim, Y. Liu, C. Gentry. “Simplified AMPX Library Capability of the CASL Neutronics Simulator MPACT,” Proc. PHYSOR 2018, Cancun, Mexico (April 22-26, 2018).
  3. A. Mohamed, C. Gentry, A. Godfrey, F. Franceschini. “VERA MPACT Depletion Validation for a Variety of PWR Fuel Types and Burnable Absorbers,” Proc. PHYSOR 2018, Cancun, Mexico (April 22-26, 2018).
  4. C. Gentry, B. Betzler, B. Collins. “Initial Benchmarking of ChemTriton and MPACT MSR Modeling Capabilities,” Trans. Am. Nucl. Soc., (2017).
  5. C. Gentry, B. Collins, A. Godfrey. “Modeling of Subcritical PWR with Fixed Neutron Source Using MPACT,” Trans. Am. Nucl. Soc., (2017).
  6. M. Jessee, W. Wieselquist, C. Gentry, U. Mertyurek. “BWR Geometry Enhancements for the Polaris Lattice Physics Code,” Trans. Am. Nucl. Soc., (2017).
  7. B. Collins, C. Gentry, A. Wysocki, R. Salko. “Molten Salt Reactor Simulations using MPACT-CTF,” Trans. Am. Nucl. Soc., 116, pp. 1170-1173 (2017).
  8. B. Collins, C. Gentry, S. Stimpson. “Molten Salt Reactor Simulations Using VERA-CS,” Proc. M&C 2017, Jeju, Korea (April 16-20, 2017).
  9. C. Gentry, A. Godfrey, T. Pandya, G. Davidson, F. Franceschini. “AP1000 Benchmarking of VERA Neutronics Toolset,” Proc. M&C 2017, Jeju, Korea (April 16-20, 2017).
  10. A. Godfrey, B. Collins, C. Gentry, J. Ritchie. “Analysis of the Startup of Watts Bar Nuclear Unit 2 using VERA,” Proc. M&C 2017, Jeju, Korea (April 16-20, 2017).
  11. C. Gentry,  I. Maldonado,  K. Kim.  “Development of Two-step Reactor Physics Analysis Procedure  for Advanced High Temperature Reactors,” Proc. PHYSOR 2016, Sun Valley, Idaho, USA (May 1-5, 2016).
  12. F. Franceschini, D. Salazar, M. Ouisloumen, A. Godfrey, S. Stimpson, B. Collins, C. Gentry. “AP1000 PWR Cycle 1 HFP Depletion Simulations with VERA-CS,” Proc. PHYSOR 2016, Sun Valley, Idaho, USA (May 1-5, 2016).
  13. C. Gentry, I. Maldonado, O. Chvala. “Burnable Poison Reactivity Control for the Advanced High Temperature Reactor,” Trans. Am. Nucl. Soc., 113, pp. 1265-1267 (2015).
  14. C. Gentry, , N. George, O. Chvala, I. Maldonado, S. Lewis, P. Avigni, B. Petrovic. “Core Physics Parametric Studies for Liquid Salt Cooled Reactors,” Trans. Am. Nucl. Soc., 108, pp. 831-833 (2013).
  15. C. Gentry, N. George, I. Maldonado, A. Godfrey, K. Terrani, J. Gehin. “Application of Fully Ceramic Micro-Encapsulated Fuels in Light Water Reactors,” Proc. ICAPP 2012, Chicago, Illinois, USA (June 24-28, 2012).
  16. C. Gentry, I. Maldonado, A. Godfrey, K. Terrani, J. Gehin. “Application of Fully Ceramic Micro- Encapsulated Fuel for Transuranic Waste Recycling in PWRs,” Proc. PHYSOR 2012, Knoxville, Tennessee, USA (April 15-20, 2012).

Technical Reports

  1. A. Godfrey, B. Collins, C. Gentry, S. Stimpson, J. Ritchie. “Watts Bar Unit 2 Startup Results with VERA,” CASL-U-2017-1306-000, Oak Ridge National Laboratory (March 31, 2017).

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