Now showing items 98-109 of 109

    • Thermal Hydraulic Analysis of a Low Enrichment Uranium Core for the MIT Research Reactor 

      Ko, Yu-Chih; Hu, Lin-Wen; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-01)
      The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for ...
    • Thermal Hydraulic and Economic Analysis of Grid-Supported Hydride and Oxide Fueled PWRs 

      Shuffler, C.; Trant, J.; Todreas, Neil E.; Romano, A. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-09)
      This report advances the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). This effort involves ...
    • Thermal-Hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor 

      Memmott, Matthew J.; Hejzlar, Pavel; Buongiorno, Jacopo (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2009-08)
      The sodium fast reactor (SFR) is currently being reconsidered as an instrument for actinide management throughout the world, thanks in part to international programs such as the Generation-IV and especially the Global ...
    • Uncertainty And Sensitivity Analysis For Long-Running Computer Codes: A Critical Review 

      Langewisch, D. R. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2010-01)
    • A Unified Risk-Informed Framework to Assess the Proliferation Risk and License the Proliferation Performace of Nuclear Energy 

      d'Oro, Edoardo Cavalieri; Golay, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
      In order to strengthen the current non-proliferation regime it is necessary to guarantee high standards of security for the sites that use, store, produce, or reprocess special nuclear materials (SNM). The current surge ...
    • UPDATE ON THE COST OF NUCLEAR POWER 

      Du, Yangbo; Parsons, John E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-05)
      We update the cost of nuclear power as calculated in the MIT (2003) Future of Nuclear Power study. Our main focus is on the changing cost of construction of new plants. The MIT (2003) study provided useful data on the ...
    • Use of Information Theory Techniques with System Dynamics Models 

      Middleton, Bobby D. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2005-09)
      Research was done to show how the output distribution of a system with random variables changes as the input distributions and other parameters are changed. Using Information Theory techniques, these different input and ...
    • Use of Performance Monitoring to Improve Reliability of Emergency Generators Diesel 

      Dulik, J. D.; Golay, M. W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1997-12)
      Emergency diesel generators are one of the most important contributors to the core damage failure rate of nuclear power plants. Current required testing and maintenance procedures are excessively strict and expensive without ...
    • Use of Response Surface for Evaluation of Functional Failure of Passive Safety System 

      Fei, Tingzhou; Golay, Michael W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-03)
      Passive safety systems are more vulnerable to their environment and initial condition due to the typical low driving forces, e.g., that of the natural circulation. We investigate the merits of different methods for ...
    • Using Risk-Based Regulations for Licensing Nuclear Power Plants: Case Study of the Gas-cooled Fast Reactor 

      Jourdan, G.; Golay, M. W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2005-12)
      The strategy adopted for national energy supply is one of the most important policy choice for the US. Although it has been dismissed in the past decades, nuclear power today has key assets when facing concerns on energy ...
    • Vented Inverted Fuel Assembly Design for an SFR 

      Vitillo, Francesco; Todreas, Neil E.; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-06)
      The goal of this work is to investigate the feasibility of a vented inverted fuel assembly for a sodium-cooled fast reactor. The inverted geometry has been previously investigated for application in Gas-cooled Fast ...
    • Wire Wrapped Hexagonal Pin Arrays for Hydride Fueled PWRs 

      Diller, Peter; Todreas, Neil E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-01)
      This work contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). Core design is ...