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  • MIT NSE: Faculty: Jacopo Buongiorno
    solid surface through which the heat transfer occurs The relevant surface features are roughness wettability hydrophilicity porosity presence of cavities size and shape of cavities and thermo physical properties of the surface material My work has been exploring the separate effects of surface roughness wettability and porosity on both Critical Heat Flux CHF and quenching heat transfer Leidenfrost point temperature This is made possible by the use of surfaces with engineered features e g posts coatings nanoparticle layers at the micro and nano scale which enabled varying the surface roughness wettability and porosity precisely and independently from each other In fabricating the test surfaces I work with Profs Michael Rubner and Robert Cohen in DMSE and ChemE respectively The offshore floating nuclear power plant We are developing an offshore floating nuclear power plant concept that achieves unprecedented levels of safety It does so through innovative design features that ensure indefinite cooling of the nuclear fuel thus reducing the likelihood of accidents with fuel damage and radionuclide release and eliminate the need for land evacuation should such an accident actually occur Both features are responsive to the new safety imperatives of a post Fukushima world This is a plant that can be entirely built and decommissioned as a floating rig in a shipyard floated to the operating site within 8 15 km of the coast anchored in relatively deep water i e 100 m and connected to the grid via an underwater transmission line The economic potential is high owing to efficient shipyard construction and decommissioning and elimination of concrete structures from the plant design wiki Patents U S Application No 61 706401 Filing Date September 27 2012 M I T Case No 15825K MIT Docket No 15825 113297 Hydrophobic Porous Coatings for Creation of Stable Vapor Films to Reduce Drag by Robert Cohen Michael Rubner Jacopo Buongiorno Harrison O Hanley and Thomas McKrell In situ treatment of metallic surfaces Provisional patent Serial Number 61 153 411 United States Patent and TM Office Filing date 18 February 2009 Nanoparticle Thin Film Coatings for Enhancement of Boiling Heat Transfer US Patent No US 2010 0224638 A1 United States Patent and TM Office Filed 10 February 2010 Concentrated solar power system International Publication No WO 2011 035232 March 24 2011 Recent Publications D Chatzikyriakou J Buongiorno D Caviezel D Lakehal DNS and LES of Turbulent Flow in a Closed Channel Featuring a Pattern of Hemispherical Roughness Elements Int J Heat Fluid Flow 53 29 43 2015 J Buongiorno D G Cahill C H Hidrovo S Moghaddam A J Schmidt L Shi Micro and Nanoscale Measurement Methods for Phase Change Heat Transfer on Planar and Structured Surfaces Nanoscale and Microscale Thermophysical Engineering 18 3 270 287 2014 R Azizian E Doroodchi T McKrell J Buongiorno L W Hu B Moghtaderi Effect of Magnetic Field on Laminar Convective Heat Transfer of Magnetite Nanofluids Int J Heat Mass Transfer 68 94 109 2014 J Buongiorno Can Corrosion and CRUD actually Improve Safety Margins in LWRs Annals

    Original URL path: http://web.mit.edu/nse/people/faculty/buongiorno.html (2016-02-01)
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  • MIT NSE: Faculty: Michael J. Driscoll
    PEOPLE Faculty Research Staff Postdocs Undergraduates Administrative Staff Women in NSE Michael J Driscoll Professor Emeritus of Nuclear Science and Engineering Emeritus mickeyd mit edu 617 253 4219 617 258 8863 fax 24 215 Education 1966 Sc D Nuclear Engineering MIT 1958 Graduate Oak Ridge School of Reactor Technology 1955 B S Chemical Engineering Carnegie Mellon Research Nuclear Waste Disposal The use of deep boreholes as a preferred alternative for disposal of nuclear high level waste spent fuel and or its reprocessed constituents has been under investigation at MIT since 1990 With the apparent demise of Yucca Mountain this alternative has taken on renewed emphasis Advanced Reactor and Fuel Cycle Development Reprocessing and recycle are not a near term prospect in the US Thus development of a cost effective i e competitive with LWRs once through core design for fast reactors would enable their near term deployment hence accelerate the transition to full breeder mode operation We have made significant progress toward this goal but more remains to be done Fast reactor capital costs must also be reduced to make them competitive MIT has pioneered in the resurrection and improvement of the supercritical CO2 Brayton power cycle which is projected to both significantly increase thermal efficiency and reduce capital cost compared to conventional Rankine cycle designs Patents M J Driscoll F L Bowman Core Catcher for Nuclear Reactor Core Meltdown Containment Pat No 4 113 560 Sept 12 1978 N E Todreas M J Driscoll P Hejzlar J Tang Passive Pressure Tube Light Water Cooled and Moderated Reactor Pat No 5 442 668 Aug 15 1995 Recent Publications Tingzhou Fei M J Driscoll E Shwageraus A Cost Effective Once Through Startup Mode for SFRs Trans Am Nucl Soc Vol 104 June 2011 K G Jensen M J Driscoll Policy Issues

    Original URL path: http://web.mit.edu/nse/people/faculty/driscoll.html (2016-02-01)
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  • MIT NSE: Faculty: Benoit Forget
    For new highly heterogeneous reactor designs the legacy methods currently available are likely not applicable Consequently a move toward full core analysis techniques that can leverage the high fidelity methods typically used for smaller problems is desired This research program focuses on reformulating the response matrix system as a nonlinear system of equations and using high performance nonlinear solvers J Roberts and B Forget Solving Eigenvalue Response Matrix Equations with Jacobian Free Newton Krylov Methods International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M C 2011 Rio de Janeiro Brazil May 8 12 2011 J Roberts and B Forget Nonlinear Coarse Mesh Transport Using the Jacobian Free Newton Krylov Method Transactions of the American Nuclear Society 102 1 533 535 2010 Energy expansion The energy variable is by far the most complex of the variables treated in deterministic simulations due to the resonant nature of the interaction probability with matter A new approach called the discrete generalized multigroup method was developed at MIT that alleviates many of the previous approximations and allows the efficient treatment of many spectral effects arising in advanced fuels and proposed reactor designs B Forget and L Zhu Mixed Energy Reactor Simulations using the Discrete Generalized Multigroup Method Nuclear Science and Engineering invited March 2011 L Zhu and B Forget An Energy Recondensation Method Using the Discrete Generalized Multigroup Energy Expansion Theory Annals of Nuclear Energy accepted April 2011 L Zhu and B Forget A Discrete Generalized Multigroup Energy Expansion Theory Nucl Sci Eng 166 2010 Reactor design and optimization Optimization techniques for reactor design and fuel cycle performance are continuously being studied by our group Additionally innovative reactor concepts such as reduced moderation boiling water reactors molten salt reactors and travelling wave reactors are being evaluated R Petroski B Forget and C Forsberg Characterizing Limited Separations Fuel Cycles Using Breed and Burn Reactors submitted Nuclear Technology March 2011 B Feng E Shwageraus B Forget and M S Kazimi Light Water Breeding with Nitride Fuel Progress in Nuclear Energy submitted October 2010 R Petroski B Forget and C Forsberg Using the Neutron Excess Concept to Determine Starting Fuel Requirements for Minimum Burnup Breed and Burn Reactors accepted Nuclear Technology November 2010 N Stauff M J Driscoll B Forget P Hejzlar Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket Nucl Tech 170 2010 B Herman E Shwageraus J Leppanen and B Forget Cross Section Generation Strategy for Advanced LWRs Proceedings of ICAPP Nice France May 2 5 2011 M Massie and B Forget Quantitative Optimization of Target Assembly Material Compositions for Isotope Management Transactions of the American Nuclear Society 103 1 746 747 2010 R Petroski B Forget and C Forsberg Neutronic Evaluation of Breed and Burn Reactor Fuel Types Using an Infinite Medium Depletion Approximation PHYSOR 2010 Pittsburgh May 2010 MIT Reactor Conversion The MIT Reactor MITR II is scheduled to convert from highly enriched uranium HEU fuel to low enriched uranium LEU fuel by 2015 under the Reduced

    Original URL path: http://web.mit.edu/nse/people/faculty/forget.html (2016-02-01)
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  • MIT NSE: Research Staff: Charles W. Forsberg
    of Wisconsin at Madison UW with assistance from Westinghouse This project was completed in December 2014 and a new 3 year FHR project was initiated with MIT UCB UW and the addition of the University of New Mexico Four major project reports have been released Commercial Basis and Commercialization Strategy Fluoride salt cooled High Temperature Reactor FHR Commercial Basis and Commercialization Strategy MIT ANP TR 153 Massachusetts Institute of Technology Cambridge MA Dec 2014 Commercial Reactor Point Design Technical Description of the Mark 1 Pebble Bed Fluoride Salt Cooled High Temperature Reactor PB FHR Power Plant UCBTH 14 002 Department of Nuclear Engineering University of California Berkeley Sept 30 2014 Test Reactor Goals Strategy and Design Fluoride salt cooled High temperature Test Reactor FHTR Goals Options Ownership Requirements Design Licensing and Support Facilities MIT ANP TR 154 Massachusetts Institute of Technology Cambridge MA Dec 2014 Final Project Report Fluoride salt cooled High Temperature Reactor for Power and Process Heat Final Project Report MIT ANP TR 157 Massachusetts Institute of Technology Cambridge MA Dec 2014 Zero Carbon and Hybrid Energy Systems Combining Nuclear Renewable and Fossil Energy Sources for Liquid Fuels and Variable Electricity Production The long term energy goals include 1 eliminating dependence on foreign oil and 2 low greenhouse gas emissions The question is how to couple nuclear with other energy sources to meet these goals pdf Options for liquid fuels production include nuclear liquid biofuels and low environmental impact nuclear shale oil production pdf The other challenge is integrating nuclear and renewable energy sources to meet variable electricity and other energy needs This requires hybrid energy systems that enable capital intensive nuclear and renewable systems to operate at full capacity while meeting variable electricity demand It involves development of technologies such as nuclear geothermal gigawatt year energy storage nuclear wind hydrogen systems and nuclear renewable shale oil electricity systems There remain major technical questions and challenges C W Forsberg Hybrid Systems to Address Seasonal Mismatches Between Electricity Production and Demand in Nuclear Renewable Electrical Grids Energy Policy 62 333 341 2013 C W Forsberg Nuclear Energy for Variable Electricity and Liquid Fuels Production Integrating Nuclear with Renewables Fossil Fuels and Biomass for a Low Carbon World MIT NES TR 015 September 2011 C W Forsberg Sustainability by combining nuclear fossil and renewable energy sources Progress in Nuclear Energy V 51 1 Jan 2009 pp 192 200 C W Forsberg Is Hydrogen the Future of Nuclear Energy Nuclear Technology V 166 1 PP 3 10 April 2009 C W Forsberg Nuclear Energy for a Low Carbon Dioxide Emission Transportation System with Liquid Fuels Nuclear Technology 164 348 367 December 2008 Nuclear Fuel Cycles Rethinking How Fuel Cycles are Organized Nuclear fuel cycles including disposal of wastes are central to nuclear power Dr Forsberg was the executive director of MIT Future of the Nuclear Fuel Cycle study that issued its report in 2011 A series of critical questions were identified that are the basis of future research One top level

    Original URL path: http://web.mit.edu/nse/people/research/forsberg.html (2016-02-01)
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  • MIT NSE: Faculty: Michael W. Golay
    and internationally particularly through use of probabilistic and dynamic methods of analysis He has also been an active advisor to governmental and industrial organizations particularly concerning risk infonned regulation and nuclear non proliferation Professor Golay received his PhD in nuclear engineering from Cornell University in 1969 and performed post doctoral research at Rennselaer Polytechnic Institute In 1980 he was a visiting researcher at Electricite de France He has served on the INPO Advisory Council the NRC s Research Review Committee the DOE s TOPS Committee on non proliferation and national laboratory and nuclear power plant oversight committees He is a Fellow of the American Association for the Advancement of Science and of the American Nuclear Society Current Research Projects Methods of Risk Informed Performance Based Safety Regulation Determination of leading organizational performance indicators Occupational risk assessment Use of subjective expertise Requirements rationalization Seismic risks Organizational Performance and Management Improvement Performance simulation methods Subjective beliefs in investment allocation Environmental and Energy Policy Contributions to improving the system of nuclear environmental protection regulation and understudy of sources of major airborne emissions and transport of airborne pollutants Teaching Interests Risk Reliability Energy Policy Engineering Design Methods Founder or co founder of over 12 academic and professional courses on subjects including energy environmental policy and nuclear power management and safety Mentor of over 80 graduate students including more than 25 PhDs Other Professional Activities Chairman of the Fission Faculty of the MIT Nuclear Engineering Dept Advisory panels for the Congress the US Nuclear Regulatory Commission Congressional Office of Technology Assessment Electric Power Research Institute EPRI and the Institute for Nuclear Power Operations INPO Consultant to over 25 firms mainly in the electric utility and nuclear industries Director of the MIT INPO Course on Nuclear Technology for Utility Executives Member American Nuclear Society American Society of Mechanical Engineers and American Association for the Advancement of Science Honors and Awards ANS Member since 1964 Northeast Local Section Chairman 1977 80 Awards Committee Standards Committee Thermal Hydraulics Division Program Committee Environmental Sciences Division Chairman 1979 80 1992 ANS Power Division Best Paper Award Fellow of the American Association for the Advancement of Science Michael W Golay is recognized for his contributions concerning nuclear power in education in improving its safety economics regulation and management and as a leader in the debate over its proper role in society Selected Recent Publications Nuclear Safety Regulation F A Felder and M W Golay Risk Analysis in Support of Improved Safety at US Dept of Energy Facilities PSAM 5 Conf Osaka Japan 2000 B Beers M W Golay and G Apostolakis Methods for Formulation of Design Basis Accidents Within a Risk Informed Approach to Safety Regulation of a New Nuclear Power Plant PSAM 5 Conf Osaka Japan 2000 L Doboe M W Golay N E Todreas and F Li A Method for Systematic Resource Allocation for Improved Nuclear Power Plant Performance PSAM 5 Conf Osaka Japan 2000 Proc Amer Nucl Soc 2000 Nuclear Power Policy and Management K F Hansen and

    Original URL path: http://web.mit.edu/nse/people/faculty/golay.html (2016-02-01)
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  • MIT NSE: Faculty: Linn W. Hobbs
    2014 EVENTS LNSP Seminar Series Rose Lecture Doctoral Research Expo Rising Stars in NSE Del Favero Prize ABOUT NSE at a glance WNSE History FAQ Diversity and Equity NSE Spotlights FUTURE OF NUCLEAR ENERGY Nuclear Fuel Cycle Report Nuclear Power Report ANS mitnse com SUPPORT NSE Mujid S Kazimi Memorial Fund Michael J Driscoll Graduate Fellowship Joseph P Kearney Memorial Fund NSE Spotlights NSE Policies Employees visitors Students Jobs For

    Original URL path: http://web.mit.edu/nse/people/faculty/hobbs.html (2016-02-01)
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  • Richard K. Lester
    of MIT s Department of Nuclear Science and Engineering leading the Department successfully through a period of rapid rebuilding and strategic renewal Professor Lester s research focuses on innovation strategy and management He is also widely known for his research on nuclear technology innovation management and control Dr Lester holds an undergraduate degree in chemical engineering from Imperial College and a Ph D in nuclear engineering from MIT He is

    Original URL path: http://web.mit.edu/nse/lester/ (2016-02-01)
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  • MIT NSE: Faculty: Ju Li
    is clearly a timescale barrier between science based simulations and practical demands such as understanding plant reliability and nuclear waste storage Energy Storage and Conversion A close coupling of in situ experimental observations with modeling has proven to be a powerful paradigm for understanding materials behavior Science 330 2010 1515 Nature 463 2010 335 Based on such fundamental understandings we are developing novel nanostructured materials for energy storage and conversion in applications such as batteries fuel cells and hydrogen embrittlement resistant steels Materials in Extreme Environments and Far from Equilibrium Materials in nuclear fission and fusion applications often involve exceptionally high stresses high temperature and high radiation flux We study the effects of radiation on microstructure and thermal electrical and mass transport properties The concept of fictive temperature s that characterize out of equilibrium materials is an intriguing statistical mechanics problem with applications in glasses and even in soft biological materials Recent Publications Nanowire Liquid Pumps J Y Huang Y C Lo J J Niu A Kushima X F Qian L Zhong S X Mao and J Li Nature Nanotechnology 2013 8 2013 277 281 A Transforming Metal Nanocomposite with Large Elastic Strain Low Modulus and High Strength S J Hao L S Cui D Q Jiang X D Han Y Ren J Jiang Y N Liu Z Y Liu S C Mao Y D Wang Y Li X B Ren X D Ding S Wang C Yu X B Shi M S Du F Yang Y J Zheng Z Zhang X D Li D E Brown and J Li Science 339 2013 1191 1194 Heterogeneously randomized STZ model of metallic glasses Softening and extreme value statistics during deformation P Y Zhao J Li and Y Z Wang Int J Plasticity 40 2013 1 22 Strain engineered artificial atom as a broad spectrum solar energy funnel J Feng X F Qian C W Huang and J Li Nature Photonics 6 2012 866 872 Quantitative fracture strength and plasticity measurements of lithiated silicon nanowires by in situ TEM tensile experiments A Kushima J Y Huang and J Li ACS Nano 6 2012 9425 9432 Adsorbate interactions on surface lead to a flattened Sabatier volcano plot in reduction of oxygen Liang Qi and Ju Li Journal of Catalysis 295 2012 59 69 Slip corona surrounding bilayer graphene nanopore Liang Qi Yunwei Mao and Ju Li Nanoscale 4 2012 5989 5997 Hydrogen embrittlement of ferritic steels Observations on deformation microstructure nanoscale dimples and failure by nanovoiding Thirumalai Neeraj Rajagopalan Srinivasan and Ju Li Acta Materialia 60 2012 5160 5171 In situ transmission electron microscopy of electrochemical lithiation delithiation and deformation of individual graphene nanoribbons Xiao Hua Liu Jiang Wei Wang Yang Liu He Zheng Akihiro Kushima Shan Huang Ting Zhu Scott X Mao Ju Li Sulin Zhang Wei Lu James M Tour and Jian Yu Huang Carbon 50 2012 3836 3844 Finding activation pathway of coupled displacive diffusional defect processes in atomistics Dislocation climb in fcc copper Sanket Sarkar Ju Li William T

    Original URL path: http://web.mit.edu/nse/people/faculty/li.html (2016-02-01)
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