Jacob Eapen
Professor of Nuclear Engineering, Associate Professor of Physics

- 919-515-5952
- jacob.eapen@ncsu.edu
- Burlington Laboratory 1114
Dr. Jacob Eapen’s interests are in science-based modeling and simulation of nuclear fuel for advanced reactors, nano-structured materials, plasma-material interactions, energy transport at nano-scales and interfaces, modeling of diffusion and viscosity in glass matrices for radioactive waste management.
Education
Nuclear Engineering
Massachusetts Institute of Technology
Nuclear Engineering
North Carolina State University
Mechanical Engineering
University of Kerala, India
Research Description
Dr. Eapen's research interests are in science-based modeling and simulation of nuclear fuel for advanced reactors, nano-structured materials, plasma-material interactions, energy transport at nano-scales and interfaces, modeling of diffusion and viscosity in glass matrices for radioactive waste management.
Publications
- Deducing Phonon Scattering from Normal Mode Excitations
- Raj, A., & Eapen, J. (2019), SCIENTIFIC REPORTS, 9. https://doi.org/10.1038/s41598-019-43306-3
- Exact diagonal representation of normal mode energy, occupation number, and heat current for phonon-dominated thermal transport
- Raj, A., & Eapen, J. (2019), JOURNAL OF CHEMICAL PHYSICS, 151(10). https://doi.org/10.1063/1.5099936
- Phonon dispersion using the ratio of zero-time correlations among conjugate variables: Computing full phonon dispersion surface of graphene
- Raj, A., & Eapen, J. (2019), COMPUTER PHYSICS COMMUNICATIONS, 238, 124–137. https://doi.org/10.1016/j.cpc.2018.12.008
- Approach to local thermodynamic equilibrium and the evolution to a glassy core following neutron/ion radiation impact
- Mei, X., Mohamed, W., & Eapen, J. (2018), PHILOSOPHICAL MAGAZINE, 98(29), 2701–2722. https://doi.org/10.1080/14786435.2018.1502482
- Computing phonon dispersion using fast zero-point correlations of conjugate variables
- Raj, A., & Eapen, J. (2018), MRS Advances, 3(10), 531–536. https://doi.org/10.1557/adv.2018.288
- Thermal jamming of ions in the superionic state of UO2
- Sanders, D., & Eapen, J. (2018), MRS Advances, 3(31), 1777–1781. https://doi.org/10.1557/adv.2018.326
- Using space-time correlations to identify transient defects
- Lowe, W., & Eapen, J. (2018), MRS Advances, 3(31), 1755–1760. https://doi.org/10.1557/adv.2018.196
- Disordering and dynamic self-organization in stoichiometric UO2 at high temperatures
- Annamareddy, A., & Eapen, J. (2017), Journal of Nuclear Materials, 483, 132–141. https://doi.org/10.1016/j.jnucmat.2016.10.042
- Entropic crossovers in superionic fluorites from specific heat
- Eapen, J., & Annamareddy, A. (2017), Ionics, 23(4), 1043–1047. https://doi.org/10.1007/s11581-017-2007-z
- Ion hopping and constrained Li diffusion pathways in the superionic state of antifluorite Li2O
- Annamareddy, A., & Eapen, J. (2017), Entropy, 19(5).
Grants
- Development of an In-Situ Testing Laboratory for Research and Education of Very High Temperature Reactor Materials
- US Dept. of Energy (DOE)(10/01/20 - 9/30/21)
- Novel Miniature Creep Tester for Virgin and Neutron Irradiated Clad Alloys with Benchmarked Multiscale Modeling and Simulations
- US Dept. of Energy (DOE)(10/01/19 - 9/30/22)
- Evaluation of the Performance of ArmaKap Ceramic Cement as a Radiation Shielding Materials with Experiments and Simulations
- ArmaKap Technologies(9/01/17 - 12/31/20)
- Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite. Work Scope Identifier: RC-2.
- US Dept. of Energy (DOE)(10/01/17 - 9/30/21)
- Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing
- US Dept. of Energy (DOE)(10/01/17 - 9/30/19)
- Turbulent MHD flow modeling in annular linear induction pumps with validation experiments
- US Dept. of Energy (DOE)(10/01/16 - 9/30/20)
- Microstructure Experiments-Enabled MARMOT Simulations of SiC/SiC-based Accident Tolerant Nuclear Fuel System
- US Dept. of Energy (DOE)(10/01/16 - 9/30/19)
- Tribological Damage Mechanisms from Experiments and Validated Simulations of Alloy 800H and Inconel 617 in a Simulated HTGR/VHTR Helium Environment
- US Dept. of Energy (DOE)(10/01/16 - 9/30/20)
- Mechanistic and Validated Creep/Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations
- US Dept. of Energy (DOE)(10/01/15 - 9/30/19)
- Aging of Used Nuclear Fuel in Storage: Accelerated Characterization and Modeling of Performance
- US Dept. of Energy (DOE)(12/15/11 - 12/15/15)