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Nicholas Brown

Nicholas Brown

Associate Professor

Biography

  • Expert in nuclear energy systems with a track record of highly effective collaboration with colleagues from diverse backgrounds
  • Experienced technical leader with excellent project and people management skills
  • Author or co-author of more than 50 articles in referred journals, and more than 100 total publications including peer-reviewed proceedings and national laboratory reports
  • Approximately 15 awards as a Principal or Co-Principal Investigator, in addition to past technical leadership on several national laboratory projects
  • US Department of Homeland Security Graduate Fellow from 2006–2009

Research

  • Nuclear reactor safety and simulation of reactor and system transients
  • Advanced nuclear fuel and cladding materials, including nuclear fuel safety
  • Assessment and simulation of sustainable nuclear fuel cycles

Education

2011    Doctor of Philosophy.  Concentration: Thermal Hydraulics

School of Nuclear Engineering, Purdue University, West Lafayette, IN, USA, Issued: May 7, 2011

2007    Master of Science in Nuclear Engineering. 

School of Nuclear Engineering, Purdue University, West Lafayette, IN, USA, Issued: Dec. 15, 2007 

2005    Bachelor of Science in Nuclear Engineering. 

Summa Cum Laude. Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM, USA, Issued: May 14, 2005


Professional Service

  • Session Co-Chair: Molten-Salt Reactor Thermal Hydraulics at Advances in Thermal Hydraulics (ATH 2018); Nov. 11-15; Orlando, Florida, USA
  • Session Chair: Current Topics in Probabilistic Risk Analysis at 2018 American Nuclear Society Winter Meeting; Nov. 11-15; Orlando, Florida, USA
  • Reactor Physics Division Executive Committee (American Nuclear Society), 2018-2021
  • Assistant Technical Program Chair, 2018 ANS Annual Meeting, Philadelphia, PA, USA
  • Session Chair: Used Fuel and Life Management for LWRs at 2018 Nuclear Fuels and Structural Materials Embedded Topical; Jun. 17-21; American Nuclear Society, Philadelphia, Pennsylvania, USA
  • Session Organizer and Chair: Nuclear Installations Safety: General - I at 2018 American Nuclear Society Annual Meeting; Jun. 17-21; Philadelphia, Pennsylvania, USA
  • Session Organizer: Current Topics in Probabilistic Risk Analysis at 2018 American Nuclear Society Annual Meeting; Jun. 17-21; Philadelphia, Pennsylvania, USA
  • Symposium Co-Organizer, Advanced ceramics and composites for nuclear fission and fusion energy, 42nd International Conference and Expo on Advanced Ceramics and Composites, 2018, Daytona, FL, USA
  • Session Organizer and Chair: Nuclear Installations Safety: General - I and II at 2017 American Nuclear Society Winter Meeting; Oct. 29 – Nov. 2; Washington D.C., USA
  • Session Organizer: Current Topics in Probabilistic Risk Analysis at 2017 American Nuclear Society Winter Meeting; Oct. 29 – Nov. 2; Washington D.C., USA
  • Nuclear Installations Safety Division Executive Committee (American Nuclear Society), 2017-2020
  • Chair, Nuclear Installations Safety Division Program Committee (American Nuclear Society), 2017-2018
  • Reactor Physics Division Program Committee (American Nuclear Society), 2015-2018
  • Session Organizer: Nuclear Installations Safety: General and Current Topics in Probabilistic Risk Analysis at 2017 American Nuclear Society Annual Meeting; Jun. 11-15; San Francisco, CA, USA
  • Session Chair of Current Topics in Probabilistic Risk Analysis at 2017 American Nuclear Society Annual Meeting; Jun. 11-15; San Francisco, CA, USA
  • Vice Chair, Nuclear Installations Safety Division Program Committee (American Nuclear Society), 2016-2017
  • Session Chair of Nuclear Installations Safety: General—I and Nuclear Installations Safety: General—III at American Nuclear Society Winter Meeting 2016, Nov. 6-10; Las Vegas, NV, USA
  • Session Chair of Molten Salt Reactor Technology and Used Fuel Separation Technology at ICAPP 2016: Nuclear Innovation: Inventing the Future of Existing and New Nuclear Power; April 17-20; San Francisco, CA, USA
  • Session Chair of Fuel Cycle and Actinide Management and Reactor Physics Experiments at PHYSOR2014: Role of Reactor Physics towards a Sustainable Future in Kyoto, Japan
  • Session Chair at FFAG'14 2014 International Workshop on FFAG Accelerators, Upton, NY, USA
  • Session Chair of Integral and Separate Thermal Hydraulics Testing and Analysis I & II at International Congress on Advances in Nuclear Power Plants 2010 in San Diego, CA, USA
  • Session Chair of General Two Phase Flow at the American Nuclear Society Winter Meeting 2006 in Albuquerque, NM, USA
  • President of Purdue Alpha Nu Sigma Nuclear Engineering Honor Society, 2009 - 2010
  • Member of American Nuclear Society and American Ceramic Society
  • Technical Peer Reviewer of U.S. DOE-NE NEUP and SBIR proposals
  • Ad-Hoc Peer Reviewer for Annals of Nuclear Energy, Nuclear Engineering and Design, Nuclear Technology, etc.

Awards and Recognitions

  • Recognized as a BNL Distinguished Performer in FY2013 and FY2014
  • Purdue University Bilsland Dissertation Fellowship, 2010–2011
  • S. Department of Homeland Security Graduate Fellowship, 2006–2009
  • Institute of Nuclear Power Operators (INPO) Fellowship, 2005–2006
  • Proposed, designed, and flew an experiment on the Vomit Comet, NASA Microgravity University Program, 2004
  • Alpha Nu Sigma and Tau Beta Pi Engineering Honor Societies
  • Accomplished actor in Albuquerque, New Mexico, community-theater, including several leading roles and numerous performances in the Albuquerque Little Theater

Publications

Select list of publications. For the full list, view his Google Scholar page.

Brown, N.R., 2020. “A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications.” Journal of Nuclear Materials, p.152139.

Burns, J.R., Hernandez, R., Terrani, K.A., Nelson, A.T., Brown, N. R.*, 2020. “Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%.” Annals of Nuclear Energy, 142, p.107423. (* Senior author)

Hernandez, R., Folsom, C. P., Woolstenhulme, N. E., Jensen, C. B., Bess, J. D., Gorton, J. P., Brown, N. R.*, 2020. “Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT,” Progress in Nuclear Energy, 123, p. 103303. (* Senior and corresponding author)

Lee, S.K., Liu, M., Brown, N. R., Terrani, K.A. and Lee, Y., 2020. “Effect of heater material and thickness on the steady-state flow boiling Critical Heat Flux,” Nuclear Technology, 206(2), pp.339-346.

Brown, N. R., Diamond, D. J., Bajorek, S., Denning, R., 2020. “Thermal-Hydraulic and Neutronic Phenomena Important in Modeling and Simulation of Liquid-Fuel Molten Salt Reactors,” Nuclear Technology, 206(2), pp.322-338.

Schappel, D., Brown, N. R., Terrani, K.A., 2019. “Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON,” Journal of Nuclear Materials, 530, p.151965.

Gorton, J.P., Collins, B.S., Nelson, A.T., Brown, N. R.*, 2019. “Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR,” Nuclear Engineering and Design, 355, p.110317. (* Senior and corresponding author)

Betzler, B.R., Heidet, F., Feng, B., Rabiti, C., Sofu, T., Brown, N. R.*, 2019. “Modeling and simulation functional needs for molten salt reactor licensing,” Nuclear Engineering and Design, 355, p.110308. (* Senior and corresponding author)

Gorton, J.P., Lee, S.K., Lee, Y., Brown, N. R.*, 2019. “Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties,” Nuclear Engineering and Design 353, p.110295. (* Senior and corresponding author)

Aly, Z., Casagranda, A., Pastore, G., Brown, N. R.*, 2019. “Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments related to hydrogen migration and redistribution in Bison,” Journal of Nuclear Materials 524, pp. 90-100. (* Senior and corresponding author)

Aly, Z., Casagranda, A., Pastore, G., Brown, N. R.*, 2019. “Variance-based sensitivity analysis applied to the hydrogen migration and redistribution model in Bison. Part II: Uncertainty quantification and optimization,” Journal of Nuclear Materials 523, pp. 478-489. (* Senior and corresponding author)

Lu, C., Brown, N. R.*, 2019. “Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost,” Nuclear Engineering and Design 347, pp.108-121. (* Senior and corresponding author)

Lu, C., Koyanagi, T., Katoh, Y., Strydom, G., Terrani, K.A., Brown, N. R.*, 2019. “Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process,” Nuclear Engineering and Design 345, pp.125-147. (* Senior and corresponding author)

Lee, S.K., Liu, M., Brown, N. R., Terrani, K.A., Blandford, E.D., Ban, H., Jensen, C.B., Lee, Y., 2019. “Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel,” International Journal of Heat and Mass Transfer 132, pp. 643-654.

Hernandez, R., Todosow, M., Brown, N. R.*, 2019. “Micro heat pipe nuclear reactor concepts: Analysis of fuel cycle performance and environmental impacts,” Annals of Nuclear Energy 126, pp. 419-426. (* Senior and corresponding author)

Cinbiz, M.N., Koyanagi, T., Singh, G., Katoh, Y., Terrani, K.A., Brown, N. R.*, 2019. “Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents,” Journal of Nuclear Materials 514, pp. 66-73. (* Senior and corresponding author)

Leandro, A.M., Heidet, F., Hu, R., Brown, N. R.*, 2019. “Thermal hydraulic model of the molten salt reactor experiment with the NEAMS system analysis module,” Annals of Nuclear Energy 126, pp. 59-67. (* Senior and corresponding author)

Singh, G., Gorton, J., Schappel, D., Brown, N. R., Katoh, Y., Wirth, B.D., Terrani, K.A., 2019. “Deformation analysis of SiC-SiC channel box for BWR applications,” Journal of Nuclear Materials 513, pp. 71-85.

Ali, A. F., Gorton, J. P., Brown, N. R., Terrani, K. A., Jensen, C. B., Lee, Y., Blandford, E. D., 2018. “Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys,” Nuclear Engineering and Design 338, pp. 218-231.

Powers, J.J., Brown, N. R., Mueller, D.E., Patton, B.W., Losa, E., Košťál, M., 2018. “Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors,” Annals of Nuclear Energy 120, pp. 319-332.

Losa, E., Košťál, M., Czakoj, T., Jánský, B., Novák, E., Rypar, V., Powers, J.J., Brown, N. R., Mueller, D., 2018. “Neutronic experiments with fluorine rich compounds at LR-0 reactor,” Annals of Nuclear Energy 120, pp. 286-295.

Lu, C., Hiscox, B.D., Terrani, K.A., Brown, N. R.*, 2018. “Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics,” Annals of Nuclear Energy 114, pp. 277-287. (* Senior and corresponding author)

Singh, G., Sweet, R., Brown, N. R., Wirth, B.D., Katoh, Y., Terrani, K., 2018. “Parametric evaluation of SiC/SiC composite cladding with UO 2 fuel for LWR applications: Fuel rod interactions and impact of nonuniform power profile in fuel rod,” Journal of Nuclear Materials 499, pp. 155-167.

Nicholas Brown

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