Nicolas Stauff joined the Argonne National Laboratory in 2012 in the Nuclear Systems Analysis department within the Nuclear Science and Engineering Division. He has been contributing to a variety of projects in the fields of reactor physics, fuel cycle analyses, and economics assessment for advanced nuclear reactors. Dr. Nicolas Stauff leads the Nuclear Applications and Economics group that supports DOE-NE, ARPA-E and the nuclear industry in these fields. Dr. Nicolas Stauff leads research on the compatibility of nuclear technologies with variable grid demand for the US DOE System Analysis and Integration Campaign. He also leads the development of a user interface to Argonne’s advanced reactors analysis codes within the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, and the user assessment of NEAMS codes capability to perform high-fidelity multiphysics simulations on micro-reactors. Finally, he is contributing to the development of advanced reactor designs in collaboration with industry (HolosGen, ARC LLC, Westinghouse, etc.).
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:
Andy Rivas, Nicolas Stauff, Tyler Sumner and Jason Hou, “Propagating Neutronic Uncertainties for FFTF LOFWOS Test #13”, Nuclear Engineering and Design, 375 (2021) 111047.
R. Ponciroli, N. E. Stauff, J. Ramsey, F. Ganda and R. B. Vilim, “An Improved Genetic Algorithm approach to the Unit Commitment/Economic Dispatch problem,” in IEEE Transactions on Power Systems, doi: 10.1109/TPWRS.2020.2986710. (2020)
Kaiyue Zeng, Nicolas Stauff, Jason Hou, T. K. Kim, “Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors,” Progress in Nuclear Energy, Vol 120, February (2020) 103184.
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 Energy, Vol. 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, Kun Mo, Yan Cao, Justin W. Thomas, Yinbin Miao, Changho Lee, Christopher Matthews, Bo Feng, “Preliminary Applications of NEAMS Codes for Multiphysics Modeling of a Heat Pipe Microreactor,” proceedings of ANS Annual 2021 meeting, June (2021).
Nicolas E. Stauff, Yinbin Miao, S. Bhattacharya, Abdellatif Yacout, Taek K. Kim “Advanced Micro-Reactor Concept Enabled by Innovative Technology,” proceedings of ANS Annual 2021 meeting, June (2021).
Nicolas E. Stauff, Yinbin Miao, Derek Kutgen, “Micro-Reactor Design for Truck Charging Station”, proceedings of ANS Winter Meeting, Chicago, Nov (2020).
Nicolas E. Stauff, Changho Lee, Ling Zou, Claudio Filippone, “Core Design of the Holos-Quad Micro Reactor”, proceedings of ANS Winter Meeting, Chicago, Nov (2020).
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,” FR’17, 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, 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.
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 FR’09, paper 1172, Kyoto, Japan (2009).