Now showing items 21-40 of 109

    • High Burnup Fuels for Advanced Nuclear Reactors 

      Oggianu, S. M.; Christensen, Holly Colleen No; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2001-05)
      The goal of this work is to select the best candidate fuel materials to deliver high burnup in advanced light water reactors. Uranium and thorium based fuels are considered. These fuel materials must be able to withstand ...
    • Analysis and Utilization of Operating Experience for Organizational Learning 

      Weil, R.; Apostolakis, George E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2001-06)
      The objective of this report is to clarify the ways that organizational factors influence nuclear power plant performance in order to improve performance. Therefore, this report studied the nuclear power plant organizational ...
    • Analysis and Utilization of Operating Experience for Organizational Learning 

      Apostolakis, G. E.; Weil, Richard (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2001-06-01)
      The objective of this report is to clarify the ways that organizational factors influence nuclear power plant performance in order to improve performance. Therefore, this report studied the nuclear power plant organizational ...
    • Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles 

      Dostal, Vaclav; Hejzlar, Pavel; Todreas, Neil E.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2001-09)
      Cost of electricity is the key factor that determines competitiveness of a power plant. Thus the proper selection, design and optimization of the electric power generating cycle is of main importance. This report makes an ...
    • MCNP4B Modeling of Pebble-Bed Reactors 

      Lebenhaft, Julian Robert (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2001-10-15)
      The applicability of the Monte Carlo code MCNP4B to the neutronic modeling of pebble-bed reactors was investigated. A modeling methodology was developed based on an analysis of critical experiments carried out at the ...
    • MODELING THE PERFORMANCE OF HIGH BURNUP THORIA AND URANIA PWR FUEL 

      Long, Y.; Kazimi, Mujid S.; Ballinger, Ronald G.; Meyer, J. E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2002-07)
      Fuel performance models have been developed to assess the performance of ThO[subscript 2]-UO[subscript 2] fuels that can be operated to a high burnup up to 80-100MWd/kgHM in current and future Light Water Reactors (LWRs). ...
    • 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 ...
    • High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report 

      Kazimi, Mujid S.; Hejzlar, Pavel; Ballinger, Ronald G.; Carpenter, David M.; Feng, Dandong; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2003-08)
      B.1.1 VIPRE modeling of PWR core with annular fuel: Optimization studies in the first year used an isolated channel and models for MDNBR analyses. These analyses provided sufficient knowledge of potential thermal hydraulic ...
    • High Performance Fuel Design for Next Generation PWRs 2nd Annual Report 

      Kazimi, Mujid S.; Hejzlar, Pavel; Ballinger, Ronald G.; Carpenter, David M.; Feng, Dandong; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2003-08)
      The overall objective of this NERI project is to examine the potential for a high performance advanced fuel design for Pressurized Water Reactors (PWRs), which would accommodate a substantial increase of core power density ...
    • Nuclear Energy Options for Hydrogen and Hydrogen-Based Liquid Fuels Production 

      Yildiz, Bilge; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2003-09)
      Nuclear energy can be used for hydrogen production through thermochemical or electrochemical processes for splitting water (and/or steam) into its elemental parts. The overall performance of alternative routes for using ...
    • Optimization of the LWR Nuclear Fuel Cycle for Minimum Waste Production 

      Shwageraus, Eugene; Hejzlar, Pavel; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2003-10)
      The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to ...
    • 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 ...
    • Design of Compact Intermediate Heat Exchangers for Gas Cooled Fast Reactors 

      Gezelius, K.; Driscoll, Michael J. ;; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-05)
      Two aspects of an intermediate heat exchanger (IHX) for GFR service have been investigated: (1) the intrinsic characteristics of the proposed compact printed circuit heat exchanger (PCHE); and (2) a specific design ...
    • Combining Thorium with Burnable Poison for Reactivity Control of a Very Long Cycle BWR 

      Inoue, Y.; Pilat, Edward E.; Xu, Z.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2004-06)
      The effect of utilizing thorium together with gadolinium, erbium, or boron burnable absorber in BWR fuel assemblies for very long cycle is investigated. Nuclear characteristics such as reactivity and power distributions ...
    • High Performance Fuel Design for Next Generation PWRs: 11th Quarterly Report 

      Kazimi, Mujid S.; Hejzlar, Pavel; Feng, Dandong; Kohse, Gordon E.; Morra, Paolo; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2004-07)
      I. Technical Narrative: The overall objective of this NERI project is to examine the potential for a high performance advanced fuel for Pressurized Water Reactors (PWRs), which would accommodate a substantial increase of ...
    • Analysis Of Flow Instabilities In Supercritical Watercooled Nuclear Reactors 

      Zhao, J.; Saha, P.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-09)
      Near the supercritical thermodynamic point, coolant density is very sensitive to temperature which gives potential to several instabilities in the supercritical water-cooled nuclear reactors. The flow stability features ...
    • NEUTRONIC AND THERMAL HYDRAULIC DESIGNS OF ANNULAR FUEL FOR HIGH POWER DENSITY BWRS 

      Morra, P.; Xu, Z.; Hejzlar, Pavel; Saha, P.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2004-12)
      As a promising new fuel for high power density light water reactors, the feasibility of using annular fuel for BWR services is explored from both thermal hydraulic and neutronic points of view. Keeping the bundle size ...
    • The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration 

      Bushman, A.; Carpenter, D. M.; Ellis, T. S.; Gallagher, S. P.; Hershcovitch, M. D.; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Space Applications, 2004-12)
      As part of the 22.033/22.33 Nuclear Systems Design project, this group designed a 100 kW[subscript e] Martian/Lunar surface reactor system to work for 5 EFPY in support of extraterrestrial human exploration efforts. The ...
    • ATTRIBUTES OF A NUCLEAR-ASSISTED GAS TURBINE POWER CYCLE 

      Jeong, Y. H.; Saha, P.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2005-02-01)
      By using a combination of a nuclear reactor, which emits no carbon dioxide, and a high efficiency natural gas turbine combined cycle (NGCC), electric utilities can reduce their generation cost as well as minimize the ...