You are here

Dean Wang

  • Associate Professor, Mechanical & Aerospace Engr
  • 201 W. 19th Ave
    E442 Scott Laboratory
    Columbus, OH 43210
  • 614-292-1337


Research interests

  • Mathematical and computational methods
  • Nuclear reactor design, modeling and simulation
  • Nuclear reactor systems and safety

Journal Articles


  • Wang, D.; Byambaakhuu, T., 2019, "High Order Lax-Friedrichs WENO Fast Sweeping Methods for the SN Neutron Transport Equation." NUCLEAR SCIENCE AND ENGINEERING
  • Forsberg, C.; Wang, D.; Shwageraus, E.; Mays, B. et al., 2019, "Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay-Heat Removal Systems that Prevent Salt Freezing." NUCLEAR TECHNOLOGY


  • Wang, D.; Xiao, S., 2018, "A linear prolongation approach to stabilizing CMFD." Nuclear Science and Engineering 190, no. 1, 45-55 - 45-55.
  • Byambaakhuu, T.; Wang, D.; Xiao, S., 2018, "A Coarse-Mesh Diffusion Synthetic Acceleration Method with Local hp Adaptation for Neutron Transport Calculations." Nuclear Science and Engineering 192, no. 2, 208-217 - 208-217.
  • Xiao, S.; Ren, K.; Wang, D., 2018, "A Local Adaptive Coarse-Mesh Nonlinear Diffusion Acceleration Scheme for Neutron Transport Calculations." NUCLEAR SCIENCE AND ENGINEERING 189, no. 3, 272-281 - 272-281.


  • Wang, D.; Yoder, G.L.; Pointer, D.W.; Holcomb, D.E., 2015, "Thermal hydraulics analysis of the Advanced High Temperature Reactor." Nuclear Engineering and Design 294, 73-85 - 73-85.


  • Ott, L.J.; Robb, K.R.; Wang, D., 2014, "Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions." Journal of Nuclear Materials 448, no. 1-3, 520-533 - 520-533.
  • Terrani, K.A.; Wang, D.; Ott, L.J.; Montgomery, R.O., 2014, "The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents." Journal of Nuclear Materials 448, no. 1-3, 512-519 - 512-519.


  • Wang, D.; Mahaffy, J.H.; Staudenmeier, J.; Thurston, C.G., 2013, "Implementation and assessment of high-resolution numerical methods in TRACE." Nuclear Engineering and Design 263, 327-341 - 327-341.


  • Wang, D.; Gauld, I.C.; Yoder, G.L.; Ott, L.J. et al., 2012, "Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool." Nuclear Technology 180, no. 2, 205-215 - 205-215.

Papers in Proceedings


  • Byambaakhuu, T.; Wang, D. "Comparison of lpCMFD with Other CMFD Based Acceleration Schemes." in 2019 ANS Student Conference. (4 2019).


  • Wang, D.; Byambaakhuu, T.; Ren, K. "A Quadratic Characteristic Method for the SN Solution." in PHYTRA4. (9 2018).
  • Wang, D.; Xiao, S.; Xu, Y.; Downar, T. et al. "Stabilizing CMFD with Linear Prolongation." in PHYSOR 2018. (4 2018).
  • Shen, Q.; Xu, Y.; Downar, T.; Wang, D. "Stability Analysis of lpCMFD for Accelerating SN method." in PHYSOR 2018. (4 2018).
  • Forsberg, C.; Wang, D.; Shwageraus, E.; Mays, B. et al. "Fluoride-Salt-Cooled High- Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Geometry and Refueling Technology." in 2018 Pacific Basin Nuclear Conference. (9 2018).


  • Wang, D.; Byambaakhuu, T. "A New Analytical SN Solution in Slab Geometry." in American Nuclear Society. (10 2017).
  • Xiao, S.; Ren, K.; Wang, D.; Xu, Y. et al. "Convergence Study of LR-NDA Using Fourier Analysis." in Transactions of the American Nuclear Society. (6 2017).


  • Ren, K.; Wang, D.; Salko, R. "Implementation of the Lax-Wendroff Method in COBRA-TF for Solving Two-Phase Flow Transport Equations." in ICAPP 2016. (4 2016).


  • Wang, D. "Solving Two-Phase Flow Transport Equations Using the Lax-Wendroff Scheme." in American Nuclear Society. (6 2015).


  • Richard, J.; Wang, D.; Yoder, G.; Carbajo, J. et al. "Implementation of Liquid Salt Working Fluids into TRACE." in ICAPP 2014. (4 2014).


  • Wang, D. "Reduce Numerical Diffusion in TRACE Using the High-Order Numerical Method ENO." in American Nuclear Society. (11 2012).