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

Monographs

Journal Articles

  • Amir F Ali, Jacob P Gorton, Nicholas Brown, Kurt A Terrani, Colby B Jensen, Youho Lee and Edward D Blandford, 2018, "Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys", Nuclear Engineering and Design, 338, pp. 218--231
  • 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
  • Evzen Losa, Ko\vst'\'al, M, T Czakoj, J\'ansk\`y, B, Evzen Novak, Vojtech Rypar, Jeffrey J Powers, Nicholas Brown and Don Mueller, 2018, "Neutronic experiments with fluorine rich compounds at LR-0 reactor", Annals of Nuclear Energy, 120, pp. 286--295
  • JJ Powers, Nicholas Brown, DE Mueller, BW Patton, E Losa, Ko\vst'\'al and 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
  • 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, Nicholas 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, Nicholas 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
  • 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
  • Nicholas Brown, Hans Ludewig, Arnold Aronson, Gilad Raitses and Michael Todosow, 2013, "Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback", Annals of Nuclear Energy, 62, pp. 548--557
  • 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
  • Nicholas Brown and Shripad T Revankar, 2012, "An endothermic chemical process facility coupled to a high temperature reactor. Part II: Transient simulation of accident scenarios within the chemical plant", Nuclear Engineering and Design, 246, pp. 266--276

Conference Proceedings

  • J P Gorton, Nicholas Brown, K A Terrani, A F Ali and Y Lee, 2018, "Evaluating Accident Tolerant Fuel Concepts in Light Water Reactors Using CASL CTF", American Nuclear Society, American Nuclear Society, pp. 17--21
  • C Lu and Nicholas Brown, 2018, "Fully Ceramic Microencapsulated Fuel in Prismatic High Temperature Gas-Cooled Reactors—Impact on Control Rod Worth and Temperature Distribution in the Core", American Nuclear Society, American Nuclear Society, pp. 17--21
  • A M Leandro, R Hu, F Heidet and Nicholas Brown, 2018, "Modeling the Molten Salt Reactor Experiment with the System Analysis Module (SAM)", Transactions of 2018 American Nuclear Society Annual Meeting; Jun. 17-21; American Nuclear Society, American Nuclear Society
  • Y Lee, E Blandford, Nicholas Brown, A F Ali, M Liu, W Marcum, D LaBrier, S Walker, G Hewitt, R Issa, C Jensen, J Strumpell and R Rebak, 2017, "A NEUP Example of US-UK Collaboration: An Experimental and Analytical Investigation into Critical Heat Flux Implications for Accident Tolerant Fuel Concepts", American Nuclear Society, American Nuclear Society, 2
  • J Carbajo, D De_Wet and Nicholas Brown, 2017, "Modeling the Molten Salt Reactor Experiment with the RELAP5-3D Code", American Nuclear Society, pp. 11--15
  • E Losa, M Koštal, V Juricek, J Uhlir, J J Powers, Nicholas Brown, D E Mueller and B W Patton, 2017, "Neutronic Tests of Fluoride Salt Based MSR/FHR Coolants", Coolants,” Transactions of 2017 American Nuclear Society Annual Meeting; Jun, American Nuclear Society, pp. 11--15
  • F Bostelmann, Nicholas Brown, A Pautz, B T Rearden, K Velkov and W Zwermann, 2017, "SCALE Multi-Group Libraries for Sodium-cooled Fast Reactor Systems"
  • A F Ali, M Liu, Nicholas Brown, K A Terrani, E D Blandford and C B Jensen, 2017, "Surface Wettability Measurements of FeCrAl Alloys Under LWR Environments", Chinese Nuclear Society, pp. 3--8
  • M N Cinbiz, K A Terrani, Nicholas Brown and K Linton, 2017, "Transient Mechanical Test Development for Accident Tolerant Cladding Candidates to Simulate PCMI-like Conditions", 2017 Water Reactor Fuel Performance Meeting Sep. 10-14; Jeju Island, South Korea: Korean Nuclear Society
  • Nicholas Brown, A Worrall and M Todosow, 2016, "Fuel Cycle Performance of Thermal Spectrum Small Modular Reactors", pp. 17--20
  • A J Wysocki, Nicholas Brown, K A Terrani and D M Wachs, 2016, "Potential Impact of Cladding Wettability on LWR Transient Progression", Transactions of 2016 American Nuclear Society Winter Meeting, American Nuclear Society
  • M S Greenwood, Nicholas Brown, B R Betzler and G T Mays, 2016, "Summary of the Workshop on Molten Salt Reactor Technologies Commemorating the 50th Anniversary of the Startup of the Molten Salt Reactor Experiment"
  • J J Carbajo, L Qualls and Nicholas Brown, 2016, "Thermal-Hydraulic Design of a Fluoride High-Temperature Demonstration Reactor", American Nuclear Society, pp. 12--16
  • A Worrall, E Sunny, M Todosow, Nicholas Brown and F Heidet, 2016, "Transition to a Thorium-Based Fuel Cycle—Choices, Challenges, and Options", American Nuclear Society
  • S Passerini, B Feng, T Fei, T K Kim, T A Taiwo, Nicholas Brown and A Cuadra, 2015, "Analysis of Transition to Fuel Cycle Systems with Continuous Recycling in Fast and Thermal Reactors"
  • S Bragg-Sitton, B Merril, J Hales, Nicholas Brown, M Todosow and K Robb, 2015, "Evaluation of Enhanced Accident Tolerant LWR Fuels"
  • Nicholas Brown and M Todosow, 2015, "Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3", American Nuclear Society
  • A Cuadra, V Bhatt, Nicholas Brown and M Todosow, 2015, "Nuclear in a Broader Energy Context – Transition Issues and Results"
  • M Todosow, Nicholas Brown, F Heidet, E Hoffman, T Taiwo, J Powers, J Gehin and R Wigeland, 2015, "Performance of Promising Thorium Fuel Cycles"
  • Nicholas Brown, M Todosow, L-Y Cheng and A Cuadra, 2015, "Screening of Reactor Performance and Safety of Fuel and Cladding Candidates with Enhanced Accident Tolerance", pp. 13--17
  • F Ganda, Nicholas Brown, H Hiruta, T K Kim, G Raitses, T Taiwo, M Todosow, R Wigeland, G Youinou and G Zhang, 2015, "Systems Using Water-cooled Reactor Technology to Achieve Fast Reactor Performance"
  • T Taiwo, T K Kim, B Feng, N Stauff, E Hoffman, F Ganda, M Todosow, Nicholas Brown, G Raitses, J Gehin, J Powers, G Youinou, H Hiruta and R Wigeland, 2015, "Tradeoffs in Fuel Cycle Performance for Most Promising Options"
  • Nicholas Brown and M Todosow, 2014, "Analysis of a Three-Stage Fuel Cycle with Heterogeneous and Homogeneous Thorium-based Fuel in Thermal Reactors and Transmutation of Transuranic Elements in an Accelerator Driven System", American Nuclear Society, pp. 9--13
  • Nicholas Brown, A Aronson and M Todosow, 2014, "BNL Metal Fuel Lattice Experiments: Candidates for Reactor Physics Benchmark Evaluation"
  • Nicholas Brown, G Raitses and M Todosow, 2014, "Fuel Cycle Analysis of Self-Sustaining Water Cooled Reactors with 232Th/233U Fuel and Impact of 233U (n,?) Cross Section Evaluations"
  • F Meot, Nicholas Brown, Haj Tahar, M Todosow, M Tsoupas and N, 2014, "High Power from Fixed-Field Rings in the ADS-Reactor Application", American Nuclear Society Winter Meeting; Nov. 9-13, American Nuclear Society
  • Nicholas Brown, L-Y Cheng and M Todosow, 2014, "Uranium Nitride Composite Fuels in a Light Water Reactor: Advanced Cladding, Nodal Core Calculations, and Transient Analysis", American Nuclear Society
  • Nicholas Brown, M Todosow and K J McClellan, 2014, "Uranium Nitride Composite Fuels in a Pressurized Water Reactor: Exploration of Multi-Batch Cycle Length and UB4 Admixture for Reactivity Control"
  • H Ludewig, A Aronson, Nicholas Brown, G Raitses and M Todosow, 2013, "Analysis of an Accelerator Driven System with Natural Uranium Fuel", American Nuclear Society

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"
  • 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
  • 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"
  • 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
  • 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
  • Nicholas Brown and M Todosow, 2014, "Reactor Performance Screening of Accident Tolerant Fuel and Cladding Candidate Systems", IAEA TECDOC SERIES, pp. 231
  • 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"
  • S Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, R Montgomery, C Stanek, M Todosow and Nicholas Brown, 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)
  • Nicholas Brown, JS Baek, A Hanson, A Cuadra, LY Cheng and D Diamond, 2014, "Irradiation Experiment Conceptual Design Parameters for NBSR Fuel Conversion"
  • S Bragg-Sitton, B Merrill, M Teague, LJ Ott, KR Robb, M Farmer, M Billone, R Montgomery, C Stanek, M Todosow and Nicholas Brown, 2013, "Advanced fuels campaign: Enhanced LWR accident tolerant fuel performance metrics", Idaho National Laboratory Report INL/EXT, pp. 13--29957
  • 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"
  • AL Hanson, Nicholas Brown and DJ Diamond, 2012, "Analysis of Lead Acceptance Elements for the NBSR"
  • 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"

Research Projects

Honors and Awards

Service

Service to Penn State:

  • Committee Work, Chairperson, Mechanical and Nuclear Engineering Department, NucE and Distinguished Seminar Series Committee, August 2017

Service to External Organizations:

  • Organizing Conferences and Service on Conference Committees, Committee Member, Reactor Physics Division Executive Committee, American Nuclear Society, July 2018 - June 2021
  • Organizing Conferences and Service on Conference Committees, Chairperson, Nuclear Installations Safety Division Program Committee, American Nuclear Society, July 2017 - June 2018
  • Organizing Conferences and Service on Conference Committees, Committee Member, Nuclear Installations Safety Division Executive Committee, American Nuclear Society, July 2017 - June 2020
  • Organizing Conferences and Service on Conference Committees, Chairperson, Vice Chair, Nuclear Installations Safety Division Program Committee, American Nuclear Society, July 2016 - June 2017
 


 

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