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Bo Feng

Manager, Reactor and Fuel Cycle Analysis


Bo Feng is a reactor and fuel cycle analysis expert at Argonne National Laboratory. His research has focused primarily on reactor physics analysis, advanced reactor core design, radiation transport, and fuel cycle systems modeling. Currently, he is leading Argonne’s research activities for NNSA’s International Plutonium Disposition program, coordinating various Molten Salt Reactor modeling and simulation efforts, modeling reactor physics for the Versatile Test Reactor, and supporting DOE-NE’s nuclear fuel cycle R&D as the lead developer for the dynamic fuel cycle systems code DYMOND. Bo has received several laboratory and national level awards for his research including Best Paper of 2009 (ANS THD), DOE’s Fuel Cycle R&D Excellence Award (2014), and Argonne Director’s Award (2016). He also served in the ANS RPD Program Committee (2014-2017). During his studies at M.I.T., he performed research in reactor physics, reduced moderation boiling water reactors, and nitride fuel performance.


  • Ph.D. Nuclear Science and Engineering, MIT, 2011
  • S.M. Nuclear Science and Engineering, MIT, 2008
  • S.B. Nuclear Science and Engineering, MIT, 2008

Research Interests

  • Core Design and Reactor Physics
  • Fuel Cycle Simulations
  • Dose Rate Calculations

Selected Publications

Feng, B., F. Heidet, E. Hoffman, and T.K. Kim, Core Design and Simulation of a Fast Spectrum Chloride Molten Salt Reactor,” 15IEMPT, Manchester, UK, September 30 – October 3 (2018).

Taiwo, T., B. Feng, E. Hoffman, T.K. Kim, and B. Dixon, Lessons Learned from Recent Nuclear Fuel Cycle Scenario Studies,” 15IEMPT, Manchester, UK, September 30 – October 3 (2018).

Edward A. Hoffman, Bo Feng, Ben Betzler, Eva Davidson, and Andy Worrall, Impact of Technology Characteristics on Transition to a Fast Reactor Fleet,” 15IEMPT, Manchester, UK, September 30 – October 3 (2018).

Feng, Bo and Nicolas Stauff, High Power Density Annular Fuel in a Fast Test Reactor,” 2018 ANS Annual Meeting, Philadelphia, PA, June (2018).

Feng, B., T. Fei, E. Hoffman, T. Kim and T. Taiwo, Transition to a Fast and Thermal Recycle Fuel Cycle with LEU Startup,” 2017 GLOBAL International Nuclear Fuel Cycle Conference, Seoul, South Korea, September 24-29 (2017).

Fei, T., B. Feng, E.A. Hoffman, T. Kim and T. Taiwo, Evaluation of a Closed Fuel Cycle Using Fast and Thermal Reactors,” 2017 GLOBAL International Nuclear Fuel Cycle Conference, Seoul, South Korea, September 24-29 (2017).

R. Eschbach, B. Feng, B. Vezzoni, F. Gabrielli, F. Alvarez-Velarde, V. Légere, F. Rocchi, G. Edwards, B. Dixon, Y. Pénéliau, R. Girieud, S. Häkkinen, T. Viitanen, A. Rätyi, E. M. Malambu, and S. Cornet, Verification of Dose Rate Calculations for PWR Spent Fuel Assemblies,” 2017 GLOBAL International Nuclear Fuel Cycle Conference, Seoul, South Korea, September 24-29 (2017).

Heidet, Florent, Bo Feng, T.K. Kim, and Temitope Taiwo, Transmutation Scoping Studies for a Chloride Molten Salt Reactor,” 14IEMPT, San Diego, CA, October 17-21 (2016).

Brown, N.R., B.W. Carlsen, B.W. Dixon, B. Feng, H.R. Greenberg, R.D. Hays, S. Passerini, M. Todosow, and A. Worrall, Identification of Fuel Cycle Simulator Functionalities,” Annals of Nuclear Energy96, 88-95 (2016).

Feng, B., B. Dixon, E. Sunny, A. Cuadra, J. Jacobson, N. Brown, J. Powers, A. Worrall, S. Passerini, and R. Gregg, Standardized Verification of Fuel Cycle Modeling,” Annals of Nuclear Energy94, 300-312 (2016).

Hoffman, E., N. Brown, B. Carlsen, B. Feng, R. Hays, G. Raitses, N. Stauff, E. Sunny, and A. Worrall, Expanded Analysis of Transition to an Alternative Fuel Cycle,” ICAPP 2016, San Francisco, CA, April (2016).

Brown, N.R., J.J. Powers, B. Feng, G. Zhang, F. Heidet, N.E. Stauff, M. Todosow, A. Worrall, J.C. Gehin, T.K. Kim, T.A. Taiwo, Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems,” Nuclear Engineering and Design289, 252-265 (2015).

Passerini, S., B. Feng, T. Fei, N. Brown, A. Cuadra, T.K. Kim, and T.A. Taiwo, Analysis of Transition to Fuel Cycle Systems with Continuous Recycling in Fast and Thermal Reactors,” GLOBAL 2015, Paris, France, September (2015).

Ganda, F., N.R. Brown, B. Feng, H. Hiruta, T.K. Kim, G. Raitses, T.A. Taiwo, M. Todosow, R. Wigeland, G.J. Youinou, and G. Zhang, Systems using Water-Cooled Reactor Technology to Achieve Fast Reactor Performance,” ICAPP 2015, Nice, France, May (2015).

Taiwo, T., T.K. Kim, B. Feng, N. Stauff, E. Hoffman, F. Ganda, M. Todosow, N. Brown, G. Raitses, J. Gehin, J. Powers, H. Hiruta, and R. Wigeland, Tradeoffs in Fuel Cycle Performance for Most Promising Options,” ICAPP 2015, Nice, France, May (2015).

Feng, B., R.N. Hill, R. Girieud, and R. Eschbach, Comparison of Gamma Dose Rate Calculations for PWR Spent Fuel Assemblies,” PHYSOR 2014, Kyoto, Japan, September (2014).

Feng, B., M.A. Smith, C.H. Lee, and T.K. Kim, Verification of ANL Physics Code Suite for Small Fast Reactor Applications,” ICAPP 2013, Jeju Island, Korea, April (2013).

Feng, B. and F. Ganda, Reducing the Void Coefficient of Reactivity in High Conversion Water Reactors,” ICAPP 2013, Jeju Island, Korea, April (2013).

Feng, B., T.K. Kim, and T.A. Taiwo, Assessment of Transition Fuel Cycle Performance with and without a Modified Open Cycle Option,” ICAPP 2012, Chicago, IL, June (2012).

Feng, B., A. Karahan, and M.S. Kazimi, Steady-State Fuel Behavior Modeling of Nitride Fuels in FRAPCON-EP,” Journal of Nuclear Materials427, 30-38 (2012).

Feng, Bo, Mujid S. Kazimi, and Benoit Forget, Feasibility of Breeding in Hard Spectrum Water Reactors with Oxide and Nitride Fuels,” Massachusetts Institute of Technology, MIT-NFC-TR-124, June (2011).

Feng, B., E. Shwageraus, B. Forget, and M.S. Kazimi, Light Water Breeding with Nitride Fuel,” Progress in Nuclear Energy53, issue 7, 862-866 (2011).

Feng, B., A. Karahan, and M.S. Kazimi, Steady-State Nitride Fuel Behavior Modeling with FRAPCON-EP and its Application to PWRs,” ICAPP 2011, Nice, France, May (2011).

Karahan, A., B. Feng, and M.S. Kazimi, Analysis of Steady state behavior of the Mixed Oxide Fuel in Reduced Moderation Boiling Water Reactor Condition with FRAPCON-EP,” ICAPP 2011, Nice, France, May (2011).

Kazimi, M.S., P. Hejzlar, Y. Shatilla, Bo Feng, Yu-Chih Ko, E. Pilat, K. Shirvan, J. Whitman, and A. Hamed, A High Efficiency and Environmentally Friendly Nuclear Reactor (HEER) for Electricity and Hydrogen,” Massachusetts Institute of Technology, MIT-ANP-TR-125, October (2009).

Guérin, L., B. Feng, P. Hejzlar, B. Forget, M.S. Kazimi, L. Van Den Durpel, A. Yacout, T. Taiwo, B. Dixon, G. Matthern, L. Boucher, M. Delpech, R. Girieud, and M. Meyer, A Benchmark Study of Computer Codes for System Analysis of the Nuclear Fuel Cycle,” Massachusetts Institute of Technology, MIT-NFC-105, April (2009).

Feng, B., J. Beccherle, P. Hejzlar, and M. Kazimi, Thermal Hydraulics of PWRs Transitioning to High Performance Annular Fuel,” NUTHOS-7, Seoul, South Korea, October (2008).

Jaeger W., V. H. Sánchez Espinoza, Bo Feng, Analysis of an XADS Target with the System Code TRACE,” IYNC 2008, Paper No. 185, Interlaken, Switzerland, September (2008). 

Feng, Bo, Pavel Hejzlar, and Mujid S. Kazimi, On the Use of High Performance Annular Fuel in PWRs,” Massachusetts Institute of Technology, MIT-NFC-TR-100, June (2008).

Kadak, A.C. and B. Feng, Conceptual Design of an Advanced Breeder Burner Reactor,” 2007 ANS Annual Meeting, Boston, MA, June (2007).