Photo of Nicholas R. Brown

Nicholas R. Brown

Assistant Professor

Affiliation(s):

  • Mechanical and Nuclear Engineering
  • Nuclear Engineering

229 Reber Building

nrb26@psu.edu

814-865-4863

Personal or Departmental Website

Research Areas:

Interest Areas:

Nuclear reactor analysis and design; nuclear reactor safety; sustainable nuclear fuel cycles; advanced reactors; advanced nuclear fuel and cladding materials; process heat applications of nuclear energy.

 
 

 

Education

  • BS, Nuclear Engineering, University of New Mexico, 2005
  • MS, Nuclear Engineering, Purdue University, 2007
  • Ph D, Nuclear Engineering, Purdue University, 2011

Publications

Book, Chapters

  • M Nedim Cinbiz, Nicholas Brown, Kurt A Terrani, Rick R Lowden, Donald Erdman and III, 2017, The Mechanical Response Evaluation of Advanced Claddings During Proposed Reactivity Initiated Accident Conditions, Springer International Publishing, pp. 355–365

Journal Articles

  • Cihang Lu, Briana D Hiscox, Kurt A Terrani and Nicholas Brown, 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
  • G Singh, R Sweet, Nicholas Brown, BD Wirth, Y Katoh and K Terrani, 2018, "Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod", Journal of Nuclear Materials, 499, pp. 155--167
  • D Petti, R Hill, J Gehin, H Gougar, G Strydom, T O’Connor, F Heidet, J Kinsey, C Grandy, A Qualls, N Brown and Others, 2017, "A Summary of the Department of Energy’s Advanced Demonstration and Test Reactor Options Study", Nuclear Technology, 199, (2), pp. 111--128
  • Joseph R Burns and Nicholas Brown, 2017, "Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts", Annals of Nuclear Energy, 110, pp. 1249--1255
  • Nicholas Brown, Andrew Worrall and Michael Todosow, 2017, "Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium", Annals of Nuclear Energy, 101, pp. 166–173
  • Nicholas Brown, Benjamin R Betzler, Juan J Carbajo, Aaron J Wysocki, M Scott Greenwood, Cole Gentry, Qualls and A Louis, 2017, "Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis", Annals of Nuclear Energy, 103, pp. 49–59
  • Nicholas Brown, Aaron J Wysocki, Kurt A Terrani, Kevin G Xu and Daniel M Wachs, 2017, "The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors", Annals of Nuclear Energy, 99, pp. 353–365
  • M Nedim Cinbiz, Nicholas Brown, Kurt A Terrani, Rick R Lowden and Donald Erdman, 2017, "A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding", Annals of Nuclear Energy, 109, pp. 396–404
  • Jacob W McMurray, Terrence B Lindemer, Nicholas Brown, Tyler J Reif, Robert N Morris and John D Hunn, 2017, "Determining the minimum required uranium carbide content for HTGR UCO fuel kernels", Annals of Nuclear Energy, 104, pp. 237–242
  • Maolong Liu, Nicholas Brown, Kurt A Terrani, Amir F Ali, Edward D Blandford and Daniel M Wachs, 2017, "Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents", Annals of Nuclear Energy, 110, pp. 48–62
  • Jeffery B Greenblatt, Nicholas Brown, Rachel Slaybaugh, Theresa Wilks, Emma Stewart and Sean T McCoy, 2017, "The Future of Low-Carbon Electricity", Annual Review of Environment and Resources, 42, (1)
  • Nicholas Brown, Brett W Carlsen, Brent W Dixon, Bo Feng, Harris R Greenberg, Ross D Hays, Stefano Passerini, Michael Todosow and Andrew Worrall, 2016, "Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle", Annals of Nuclear Energy, 96, pp. 88–95
  • Qualls, A Louis, Benjamin R Betzler, Nicholas Brown, Juan J Carbajo, M Scott Greenwood, Richard Hale, Thomas J Harrison, Jeffrey J Powers, Kevin R Robb, Jerry Terrell and others, 2016, "Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview", Annals of Nuclear Energy
  • B Feng, B Dixon, E Sunny, A Cuadra, J Jacobson, N R Brown, J Powers, A Worrall, S Passerini and R Gregg, 2016, "Standardized verification of fuel cycle modeling", Annals of Nuclear Energy, 94, pp. 300–312
  • Nicholas Brown, Jeffrey J Powers, Michael Todosow, Massimiliano Fratoni, Hans Ludewig, Eva E Sunny, Gilad Raitses and Arnold Aronson, 2016, "Thorium Fuel Cycles with Externally Driven Systems", Nuclear Technology, 194, (2), pp. 233–251
  • Florent Heidet, Nicholas Brown and Malek Haj Tahar, 2015, "Accelerator–Reactor Coupling for Energy Production in Advanced Nuclear Fuel Cycles", Reviews of Accelerator Science and Technology, 8, pp. 99–114
  • JS Baek, A Cuadra, L-Y Cheng, AL Hanson, NR Brown and DJ Diamond, 2015, "Analysis of Loss-of-Flow Accidents for the NIST Research Reactor with Fuel Conversion from HEU to LEU", Nuclear Technology, 189, (1), pp. 71–86
  • Nicholas Brown, Michael Todosow and Arantxa Cuadra, 2015, "Screening of advanced cladding materials and UN–U 3 Si 5 fuel", Journal of Nuclear Materials, 462, pp. 26–42
  • Nicholas Brown, J. J. Powers, B. Feng, F. Heidet, N. E. Stauff, G. Zhang, M. Todosow, A. Worrall, J. C. Gehin, T.K. Kim and others, 2015, "Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems", Nuclear Engineering and Design, 289, pp. 252–265
  • JS Baek, A Cuadra, L-Y Cheng, AL Hanson, NR Brown and DJ Diamond, 2014, "Analysis of Reactivity Insertion Accidents for the NIST Research Reactor Before and After Fuel Conversion", Nuclear Technology, 185, (1), pp. 1–20
  • DJ Diamond, JS Baek, AL Hanson, LY Cheng, Nicholas Brown and A Cuadra, 2014, "Conversion Preliminary Safety Analysis Report for the NIST Research Reactor", Brookhaven National Laboratory, Upton, NY
  • Nicholas Brown, Albert L Hanson and David J Diamond, 2014, "Impact of Local Burnup on Prediction of Power Density in the NIST Research Reactor", Nuclear Technology, 187, (1), pp. 103–116
  • Nicholas Brown, Arnold Aronson, Michael Todosow, Ryan Brito and Kenneth J McClellan, 2014, "Neutronic performance of uranium nitride composite fuels in a PWR", Nuclear Engineering and Design, 275, pp. 393–407
  • LY Cheng, A Cuadra and Nicholas Brown, 2014, "PWR Plant Model to Assess Performance of Accident Tolerant Fuel in Anticipated Transients and Accidents", IAEA TECDOC SERIES, pp. 211
  • NR Brown and M Todosow, 2014, "Reactor Performance Screening of Accident Tolerant Fuel and Cladding Candidate Systems", IAEA TECDOC SERIES, pp. 231
  • S Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, R Montgomery, C Stanek, M Todosow and others, 2014, "Advanced Fuels Campaign: LWR Accident Tolerant Fuel Performance Metrics", Idaho National Laboratory, Advanced Fuels Campaign, FCRDFUEL-2013-000264, INL/EXT-13-30226 (February 2014)
  • S Bragg-Sitton, B Merrill, M Teague, LJ Ott, KR Robb, M Farmer, M Billone, R Montgomery, C Stanek, M Todosow and others, 2013, "Advanced fuels campaign: Enhanced LWR accident tolerant fuel performance metrics", Idaho National Laboratory Report INL/EXT, pp. 13--29957
  • Nicholas Brown, Hans Ludewig, Arnold Aronson, Gilad Raitses and Michael Todosow, 2013, "Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients", Annals of Nuclear Energy, 62, pp. 538–547
  • AL Hanson, Nicholas Brown and DJ Diamond, 2012, "Analysis of Lead Acceptance Elements for the NBSR"
  • ST Revankar and Nicholas Brown, 2012, "Coupling of SI thermochemical cycle models to thermic"
  • DJ Diamond, AL Hanson, JS Baek, Nicholas Brown, A Cuadra, LY Cheng, DS O’Kelly, RE Williams and JM Rowe, 2012, "Progress with the Conversion of the NIST Research Reactor"
  • Nicholas Brown and Shripad T Revankar, 2012, "A review of catalytic sulfur (VI) oxide decomposition experiments", international journal of hydrogen energy, 37, (3), pp. 2685–2698
  • Nicholas Brown, Volkan Seker, Shripad T Revankar and Thomas J Downar, 2012, "An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant", Nuclear Engineering and Design, 246, pp. 256–265
  • Nicholas Brown, Volkan Seker, Shripad T Revankar and Thomas J Downar, 2012, "Transient simulation of an endothermic chemical process facility coupled to a high temperature reactor: Model development and validation", Nuclear Engineering and Design, 248, pp. 1–13
  • Nicholas Brown and Shripad T Revankar, 2011, "Chemical Plant Accidents in a Nuclear Hydrogen Generation Scheme", Trans. of Korean Nuclear Society
  • Nicholas Brown and Shripad T Revankar, 2011, "Safety Philosophy in Process Heat Plants Coupled to High Temperature Reactors", Trans. of Korean Nuclear Society
  • Nicholas Brown, 2011, "Study of hydrogen generation plant coupled to high temperature gas cooled reactor"
  • Nicholas Brown, Shripad T Revankar, Volkan Seker, Thomas J Downar and others, 2010, "Proposed chemical plant initiated accident scenarios in a sulphur-iodine cycle plant coupled to a pebble bed modular reactor", Nuclear Science, pp. 377--386
  • Nicholas Brown, Volkan Seker, Seungmin Oh, Shripad T Revankar, Thomas J Downar, Cheikhou Kane and others, 2010, "Transient modelling of sulphur-iodine cycle thermochemical hydrogen generation coupled to pebble bed modular reactor", Nuclear Science, pp. 363--376
  • Nicholas Brown, Seungmin Oh, Shripad T Revankar, Cheikhou Kane, Salvador Rodriguez, Randall Cole, Jr and Randall Gauntt, 2009, "Analysis model for sulfur-iodine and hybrid sulfur thermochemical cycles", Nuclear Technology, 166, (1), pp. 43--55
  • Nicholas Brown, Seungmin Oh, Shripad T Revankar, Karen Vierow, Salvador Rodriguez, Randall Cole, Jr and Randall Gauntt, 2009, "Simulation of sulfur-iodine thermochemical hydrogen production plant coupled to high-temperature heat source", Nuclear Technology, 167, (1), pp. 95--106
  • Seungmin OH, Shripad T REVANKAR, Nicholas Brown, Karen VIEROW, Salvador RODRIGUEZ, Randall COLE and Randall GAUNTT, 2006, "Assessment of sulfur iodine thermochemical water splitting process flowsheet with ASPEN code", Transactions of the American Nuclear Society, 94, pp. 625--626
  • Steven A Wright, Nicholas Brown and Andrew J MARCH, 2006, "Measured and modeled turbomachinery operating characteristics in a closed-brayton cycle test loop", Transactions of the American Nuclear Society, 95, pp. 855--857
  • Shripad T Revankar, Seungmin Oh, Nicholas Brown, Karen VIEROW, Salvador RODRIGUEZ, Randall COLE and Randall GAUNTT, 2006, "Simplified model to couple SI cycle to nuclear heat transport system", Transactions of the American Nuclear Society, 94, pp. 623--624
  • Seungmin OH, Nicholas Brown, Shripad T REVANKAR, Karen VIEROW, Salvador RODRIGUEZ, Randall COLE and Randall GAUNTT, 2006, "Transient model for SI cycle hydrogen generating plant coupled to high temperature gas cooled reactor", Transactions of the American Nuclear Society, 95, pp. 901--902

Conference Proceedings

  • Nicholas Brown, S Oh and ST Revankar, 2006, "Simulation of Heat Exchanger Transients in Sulfuric-Acid and Hydrogen-Iodide Decomposition", pp. 111--118
  • Ronald J Lipinski, Steven A Wright, Daniel J Dorsey, Curtis D Peters, Nicholas Brown, Joshua Williamson and Jennifer Jablonski, 2005, "A Gas-Cooled-Reactor Closed-Brayton-Cycle Demonstration with Nuclear Heating", 746, (1), pp. 437--448
  • Steven A Wright, Robert Fuller, Ronald J Lipinski, Kenneth Nichols and Nicholas Brown, 2005, "Operational Results of a Closed Brayton Cycle Test-Loop", 746, (1), pp. 699--710

Technical Reports

  • Jeffrey J Powers, Nicholas Brown, Don Mueller, Bruce W Patton, Losa, Ev\vzen, Ko\vst'\'al and Michal, 2017, "Comparing Sensitivity/Uncertainty Analysis Results for LR-0 Salt Experiments with Salt Reactor Models"
  • Benjamin R Betzler, Jeffrey J Powers and Nicholas Brown, 2017, "Implementation of Molten Salt Reactor Tools in SCALE"
  • Randy Belles, Willis P Poore, III, Nicholas Brown, George F Flanagan, Mark Holbrook, Wayne Moe and Tanju Sofu, 2017, "Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors"
  • Nicholas Brown, Jeffrey J Powers, Don Mueller and Bruce W Patton, 2016, "Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models"
  • A Qualls, Nicholas Brown, Benjamin R Betzler, Juan Carbajo, Richard Edward Hale, Thomas J Harrison, Jeffrey J Powers, Kevin R Robb, Jerry W Terrell and A. Wysocki, 2016, "Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design"
  • Nicholas Brown, William David Pointer, Matt Sieger, George F Flanagan, Wayne Moe and Mark Holbrook, 2016, "Qualification of Simulation Software for Safety Assessment of Sodium Cooled Fast Reactors: Requirements and Recommendations"
  • M\'eot, F, A Aronson, M Bai, D Brown, Nicholas Brown, M Haj Tahar, M Herman, A Hershcovitch, B Horak, H Ludewig and others, 2016, "A Summary of an Inter-Directorate C-AD/NSTD “Accelerator Driven Subcritical Reactor” Collaboration"
  • Nicholas Brown, AL Qualls, Benjamin R Betzler, Juan J Carbajo, Michael Scott Greenwood, R Hale, Thomas J Harrison, Jeffrey J Powers and Kevin R Robb, 2016, "Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor"
  • E Hoffman, Nicholas Brown, B Carlsen, B Feng, R Hays, G Raitses, N Stauff, E Sunny and A Worrall, 2016, "Expanded Analysis of Transition to an Alternative Fuel Cycle"
  • Nicholas Brown, Aaron J Wysocki and Kurt A Terrani, 2016, "Reactivity Initiated Accident Simulation to Inform Transient Testing of Candidate Advanced Cladding"
  • Stefano Passerini, Bo Feng, Tingzhou Fei, Taek K Kim, Temitope A Taiwo, Nicholas Brown and Arantxa Cuadra, 2015, "Analysis of Transition to Fuel Cycle System with Continuous Recycling in Fast and Thermal Reactors"
  • A Qualls, B Betzler, Nicholas Brown, Juan Carbajo, M Greenwood, R Hale, T Harrison, J Powers, K Robb and J Terrell, 2015, "Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor"
  • Ehud Greenspan, Phillip M Gorman, Sandra Bogetic, Jeffrey E Seifried, Guanheng Zhang, Christopher R Varela, Massimiliano Fratoni, Jasmina J Vijic, Thomas Downar, Andrew Hall and others, 2015, "Self-Sustaining Thorium Boiling Water Reactors"
  • Brad Merrill, Melissa Teague, Robert Youngblood, Larry Ott, Kevin Robb, Michael Todosow, Chris Stanek, Mitchell Farmer, Michael Billone, Robert Montgomery and others, 2014, "Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics"
  • Nicholas Brown, JS Baek, A Hanson, A Cuadra, LY Cheng and D Diamond, 2014, "Irradiation Experiment Conceptual Design Parameters for NBSR Fuel Conversion"
  • AL Hanson, Nicholas Brown and DJ Diamond, 2013, "Effect of Shim Arm Depletion in the NBSR"
  • Nicholas Brown, AL Hanson and DJ Diamond, 2013, "Local Burn-Up Effects in the NBSR Fuel Element"
  • DJ Diamond, J Baek, AL Hanson, LY Cheng, Nicholas Brown and A Cuadra, 2013, "Planning Document for an NBSR Conversion Safety Analysis Report"
  • Simone Massara, Shannon Bragg-Sitton, Lori Braase, Brad Merrill, Melissa Teague, Chris R Stanek, Robert H Montgomery, Larry J Ott, Kevin Robb, Lance Snead and others, 2013, "Proceedings of the Second OECD/NEA Organisation Meeting on Increased Accident Tolerance of Fuels for LWRs"
  • J Baek, D Diamond, A Cuadra, AL Hanson, LY Cheng and Nicholas Brown, 2012, "Accident Analysis for the NIST Research Reactor Before and After Fuel Conversion"
  • Shripad T Revankar, Nicholas Brown, Cheikhou Kane and Seungmin Oh, 2010, "Development of Efficient Flowsheet and Transient Modeling for Nuclear Heat Coupled Sulfur Iodine Cyclefor Hydrogen Production"
  • Andrew March and Nicholas Brown, 2006, "Generation IV power production systems and advanced nuclear power conversion concepts: analysis and evaluation of the Sandia-Brayton loop."
  • Jennifer A Jablonski, Joshua J Williamson, Steven Alan Wright, Daniel John Dorsey, Nicholas Brown, Curtis D Peters and Ronald J Lipinski, 2004, "A gas-cooled-reactor closed-Brayton-cycle demonstration with nuclear heating."
  • Joshua J Williamson, Jennifer A Jablonski, Steven Alan Wright, Daniel John Dorsey, Nicholas Brown, Curtis D Peters and Ronald J Lipinski, 2004, "A gas-cooled-reactor closed-Brayton-cycle demonstration with nuclear heating."
  • Robert Fuller, Steven Alan Wright, Kenneth Graham Nichols, Nicholas Brown and Ronald J Lipinski, 2004, "Operational results of a Closed Brayton Cycle test-loop."

Other

  • D Petti, R Hill, J Gehin, H Gougar, G Strydom, F Heidet, J Kinsey, C Grandy, A Qualls, Nicholas Brown and others, 2016, "Advanced Demonstration and Test Reactor Options Study", INL/EXT-16-37867, Idaho National Laboratory

Research Projects

  • October 2017 - September 2020, "An Experimental and Analytical Investigation into Critical Heat Flux (CHF) Implications for Accident Tolerant Fuel (ATF) Concepts," (Sponsor: New Mexico, University of).
  • October 2017 - September 2020, "Development of a Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation," (Sponsor: U.S. Department of Energy).

Honors and Awards

  • Bilsland Dissertation Fellowship, Purdue University, 2010 - 2011
  • Graduate Fellowship, U.S. Department of Homeland Security, 2006 - 2009
  • Institute of Nuclear Power Operators Fellowship, INPO, 2005 - 2006

Service

Service to Penn State:

  • Chairperson, Mechanical and Nuclear Engineering Department, NucE and Distinguished Seminar Series Committee, August 2017 - July 2018

Service to External Organizations:

  • Committee Member, Nuclear Installations Safety Division Executive Committee, American Nuclear Society, July 2017 - June 2020
  • Committee Member, Reactor Physics Division Program Committee, American Nuclear Society, 2015 - 2018
  • Chairperson, Nuclear Installations Safety Division Program Committee, American Nuclear Society, July 2017 - June 2018
  • Co-Organizer, Advanced ceramics and composites for nuclear fission and fusion energy, 42nd International Conference and Expo on Advanced Ceramics and Composites, 2018, 2017 - 2018
  • Chairperson, Vice Chair, Nuclear Installations Safety Division Program Committee, American Nuclear Society, July 2016 - June 2017
  • Chairperson, Nuclear Installations Safety: General I & II, 2017 American Nuclear Society Winter Meeting; Oct. 29- Nov. 2, November 2017
  • Organizer, Nuclear Installations Safety: General I & II and Current Topics in Probabilistic Risk Analysis, 2017 American Nuclear Society Winter Meeting; Oct. 29- Nov. 2, November 2017
  • Chairperson, Current Topics in Probabilistic Risk Analysis, 2017 American Nuclear Society Annual Meeting; Jun. 11-15, June 2017
  • Organizer, Nuclear Installations Safety: General and Current Topics in Probabilistic Risk Analysis, 2017 American Nuclear Society Annual Meeting; Jun. 11-15, June 2017
  • Chairperson, Nuclear Installations Safety: General—I and Nuclear Installations Safety: General—III, American Nuclear Society Winter Meeting 2016, Nov. 6-10, November 2016
  • Chairperson, 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, April 2016
  • Chairperson, Fuel Cycle and Actinide Management and Reactor Physics Experiments, PHYSOR2014: Role of Reactor Physics towards a Sustainable Future, 2014
  • Chairperson, Integral and Separate Thermal Hydraulics Testing and Analysis I & II, International Congress on Advances in Nuclear Power Plants, 2010
  • President, Purdue Alpha Nu Sigma Nuclear Engineering Honor Society, 2009 - 2010
  • Chairperson, General Two Phase Flow, American Nuclear Society Winter Meeting, 2006
  • DemonstratorUniversity of New Mexico Nuclear Science Workshop for middle and high school science teachers, 2003
 


 

About

The Department of Mechanical and Nuclear Engineering at Penn State is one of the nation’s largest and most successful engineering departments. We serve more than 1,000 undergraduate students and more than 330 graduate students

We offer B.S. degrees in mechanical engineering and nuclear engineering as well as resident (M.S., Ph.D.) and online (M.S., M.Eng.) graduate degrees in nuclear engineering and mechanical engineering. MNE's strength is in offering hands-on experience in highly relevant research areas, such as energy, homeland security, biomedical devices, and transportation systems.

Department of Mechanical and Nuclear Engineering

137 Reber Building

The Pennsylvania State University

University Park, PA 16802-4400

Phone: 814-865-2519