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

  • 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, NR 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
  • 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
  • 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

Technical Reports

  • 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"
  • 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"

Research Projects

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:

  • Committee Member, Nuclear Engineering Faculty Search Committee, July 2017 - May 2018
  • 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
  • Chairperson, Vice Chair, Nuclear Installations Safety Division Program Committee, American Nuclear Society, July 2016 - June 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