Skip to main content

Nicolas E. Stauff

Principal Nuclear Engineer

Nuclear Engineer in Reactor Physics and Fuel Cycle Analysis



Nicolas Stauff joined Argonne National Laboratory in 2012 in the Nuclear Systems Analysis group within the Nuclear Science and Engineering Division. He is contributing to a variety of projects in the fields of reactor physics and fuel cycle analyses for advanced nuclear reactors. Dr. Nicolas Stauff contributes to the US DOE System Analysis and Integration Campaign for which he is leading research on the compatibility of nuclear technologies with variable grid demand. He also works on various international collaborations: with CIAE (China) on the modeling of the CEFR reactor, with CEA (France) on the modeling of the ASTRID project, and with JAEA (Japan) on the development of the JSFR. Dr. Nicolas Stauff leads the development of a user interface to Argonne’s advanced reactors analysis codes within the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. He is contributing to the design of the Versatile Test Reactor and working with nuclear startup companies (ARC, HolosGen…) on the development of their reactor designs. He is especially interested in approaches to improve the inherent safety and flexible operation of nuclear reactors.

Before joining Argonne, Dr. Nicolas Stauff performed research at the Massachusetts Institute of Technology (MIT), and at the French Atomic Energy Commission (CEA) on designing advanced fast neutron reactors with carbide fuel. He received his Ph.D. in nuclear engineering from the University of Paris XI and his M.S and B.S. in electrical engineering from the SUPELEC school in France.


  • 2011: Ph.D. in Nuclear Engineering from the Paris XI university, France.
  • 2009: Master in Nuclear Engineering from the INSTN school of the French Atomic Energy Commission (CEA), France.
  • 2008: Bachelor and Master in Electrical Engineering from Supélec, France

Selected peer-reviewed publications:

International Reports

Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes, OECD Nuclear Energy Agency, February 2016, NEA/NSC/R(2015)9.


N. E. Stauff, T. K. Kim, T. A. Taiwo, Variations in Nuclear Waste Management Performance of Various Fuel-Cycle Options,” Journal of Nuclear Science and Technology, DOI: 10.1080/00223131.2015.1032380

N. E. Stauff, L. Buiron, B. Fontaine, G. Rimpault, Methodology for Designing a Sodium-cooled Fast Reactor with Inherent Safety,” Nuclear Technology, 181, February (2013).

C. Fiorina, N. E. Stauff, F. Franceschini, M.T. Wenner, A. Stanculescu, T.K. Kim, A. Cammi, M.E. Ricotti, R.N. Hill, T.A. Taiwo, M. Salvatores, Comparative Analysis of Thorium and Uranium Fuel for Transuranic Recycle in a Sodium Cooled Fast Reactor,” Annals of Nuclear EnergyVol. 62, pp. 26-39 (2013).

N. E. Stauff, M. J. Driscoll, P. Hejzlar, B. Forget, Resolution of proliferation issues for a sodium fast reactor blanket,” Nuclear Technology, 170, 371-382, June (2010).


Nicolas E. Stauff, Taek K. Kim, Robert A. Lefebvre, Brandon R. Langley, Bradley T. Rearden, Integration of the Argonne Reactor Computation codes into the NEAMS Workbench,” ANS Summer meeting, Philadelphia, PA, USA, June 17-21, (2018).

Nicolas E. Stauff, Robert A. Lefebvre, Laura Swiler, Bradley T. Rearden, Coupling of DAKOTA with the ARC suite of codes in the NEAMS Workbench for Uncertainty Quantification,” ANS Summer meeting, Philadelphia, PA, USA, June 17-21, (2018).

Nicolas E. Stauff, K. Zeng, G. Zhang, G. Aliberti, J. Hu, T. Fanning, and T. K. Kim, Uncertainty quantification of ABR transient safety analysis – nuclear data uncertainties,” BEPU 2018, May 13-19, Lucca, Italy (2018).

Nicolas E. Stauff, Roberto Ponciroli, Taek K. Kim and Temitope A. Taiwo, Benefits of the Sodium-cooled Fast Reactor Technology for Load Following Applications,” FR17, Yekaterinburg, Russia (2017).

Nicolas E. Stauff, Paul K. Romano, Chang H. Lee, and Taek K. Kim, Verification of Mixed Stochastic/Deterministic Approach for Fast and Thermal Reactor Analysis,” Proceedings of ICAPP, Fukui & Kyoto, April (2017).

Nicolas E. Stauff, E. Hoffman, T. K. Kim, T. A. Taiwo, Impact of Fast Reactor Technology on U/Pu and U/TRU Continuous Recycle Fuel Cycles,” Proceeding of PHYSOR 2016, paper 16061, Sun Valley, May 1-5, (2016).

Nicolas E. Stauff, T. K. Kim, T. A. Taiwo, R. A. Wigeland, Assessment of a closed fuel cycle using less attractive material in a Small Modular Fast Reactor,” Proceedings of ANS Winter Meeting, paper 11577 Anaheim, CA (2014)

Nicolas E. Stauff, T. K. Kim, D. Yun, T. A. Taiwo, H. S. Khalil, Application of an Annular Metallic Fuel with Lower Gas Plenum for Sodium-cooled Fast Reactor”, Proceedings of ANS summer conference, paper 110113, Atlanta, June 2013. [Received best paper award from the ANS Reactor Physics Division]

Nicolas E. Stauff, C. Fiorina, F. Franceschini, T. K. Kim, T. A. Taiwo, Analysis of Fuel Options for the ARR Breakeven Core Configuration,” Proceedings of GLOBAL2013, paper 8221, Salt Lake City, USA (2013).

F. Varaine, Nicolas E. Stauff, M. Masson, M. Pelletier, G. Mignot, A. Zaetta, J. Rouault, Comparative review on different fuels for GEN IV Sodium Fast Reactors: merits and drawbacks,” Proceedings of FR09, paper 1172, Kyoto, Japan (2009).