Browsing Center for Advanced Nuclear Energy Systems (CANES) by Title

Now showing items 87-106 of 109

    • Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor 

      Romano, A.; Todreas, Neil E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-06)
      In order to fulfill the goals set forth by the Generation IV International Forum, the current NERI funded research has focused on the design of a Gas-cooled Fast Reactor (GFR) operating in a Breed and Burn (B&B) fuel ...

    • A Semi-Passive Containment Cooling System Conceptual Design 

      Liu, H.; Todreas, N. E.; Driscoll, M. J.; Byun, C. S.; Kim, Y. H.; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1998-02)
      The objective of this project was to investigate a passive containment cooling system (PCCS) for the double concrete containment of the Korean Next Generation Reactor (KNGR). Two conceptual PCCS designs: the thermosyphon ...

    • Sensitivity of Economic Performance of the Nuclear Fuel Cycle to Simulation Modeling Assumptions 

      Bonnet, Nicephore; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2007-07)
      Comparing different nuclear fuel cycles and assessing their implications requires a fuel cycle simulation model as complete and realistic as possible. In this report, methodological implications of modeling choices are ...

    • Stability Analysis of Natural Circulation in BWRs at High Pressure Conditions 

      Hu, Rui; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2007-10)
      At rated conditions, a natural circulation boiling water reactor (NCBWR) depends completely on buoyancy to remove heat from the reactor core. This raises the issue of potential unstable flow oscillations. The objective ...

    • Stability Analysis of Supercritical Water Cooled Reactors 

      Zhao, J.; Saha, P.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2005-09)
      The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500ºC average core exit). The high coolant temperature as it leaves the ...

    • Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments 

      Gibbs, Jonathan Paul; Ballinger, Ronald; Ballinger, Ronald (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
      Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

    • A Super Critical Carbon Dioxide Cycle for Next Generation Nuclear Reactors 

      Dostal, Vaclav; Driscoll, Michael J.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-03)
      A systematic, detailed major component and system design evaluation and multiple-parameter optimization under practical constraints has been performed of the family of supercritical CO[subscript 2] Brayton power cycles for ...

    • A System Dynamics Model of the Energy Policymaking Process 

      Oggianu, Stella Maris; Hansen, Kent F. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2002-08)
      Electric energy is a fundamental commodity for any aspects of the modern world. However, there are many uncertainties in the sources of electricity that are going to be used in the future. Some of these uncertainties are ...

    • A System Dynamics Model of the Energy Policymaking Process 

      Oggianu, Stella Maris; Hansen, Kent F. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2002-08-01)
      Electric energy is a fundamental commodity for any aspects of the modern world. However, there are many uncertainties in the sources of electricity that are going to be used in the future. Some of these uncertainties are ...

    • A System Dynamics Study of the Nuclear Fuel Cycle with Recycling: Options and Outcomes for the US and Brazil 

      Busquim e Silva, R.; Kazimi, Mujid S.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-11)
      A system dynamics simulation technique is applied to generate a new version of the CAFCA code to study mass flows in the nuclear fuel cycle, and the impact of different options for advanced reactors and fuel recycling ...

    • A Systematic Study of Moderation Effects On Neutronic Performance of UO[subscript 2] Fueled Lattices 

      Xu, Z.; Driscoll, Michael J.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2001-05)
      This report addresses the physics of reactor cores that can be operated for 10 to 15 years without refueling — inspired by the objective of enhanced nuclear fuel cycle performance with regard to economics and resistance ...

    • 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 ...