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

Now showing items 56-75 of 109

    • Impact of Alternative Nuclear Fuel Cycle Options on Infrastructure and Fuel Requirements, Actinide and Waste Inventories, and Economics 

      Guérin, Laurent; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-09)
      The nuclear fuel once-through cycle (OTC) scheme currently practiced in the U.S. leads to accumulation of uranium, transuranic (TRU) and fission product inventories in the spent nuclear fuel. Various separation and ...

    • Innovative Fuel Designs for High Power Density Pressurized Water Reactor 

      Feng, D.; Kazimi, Mujid S.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-09)
      One of the ways to lower the cost of nuclear energy is to increase the power density of the reactor core. Features of fuel design that enhance the potential for high power density are derived based on characteristics of ...

    • An Integrated Formal Approach for Developing High Quality Software for Safety-Critical Systems 

      Ouyang, Meng; Golay, Michael W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1995-09)
      This report presents the results of a study which devises an Integrated Formal Approach (IFA) for improving specifications of the designs of computer programs used in safety-critical systems. In this IFA, the formal ...

    • Investigation of Pressure-Tube and Calandria-Tube Deformation Following a Single Channel Blockage Event in ACR-700 

      Gerardi, Craig Douglas; Buongiorno, Jacopo (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2005-11)
      The ACR-700 is an advanced pressure-tube (PT) reactor being developed by Atomic Energy of Canada Limited (AECL). As in conventional CANDU reactors, the PTs are horizontal. Each PT is surrounded by a calandria tube (CT), ...

    • Investigation of Pressure-Tube and Calandria-Tube Deformation Following a Single Channel Blockage Event in ACR-700 

      Gerardi, C.; Buongiorno, J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2005-11)
      The ACR-700 is an advanced pressure-tube (PT) reactor being developed by Atomic Energy of Canada Limited (AECL). As in conventional CANDU reactors, the PTs are horizontal. Each PT is surrounded by a calandria tube (CT), ...

    • 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 ...

    • 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 ...

    • MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program 

      Xu, Z.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-12)
      MCODE Version 2.2 is a linkage program, which combines the continuous-energy Monte Carlo code, MCNP-4C, and the one-group depletion code, ORIGEN2, to perform burnup calculations for nuclear fission reactor systems. MCNP ...

    • Methods for Comparative Assessment of Active and Passive Safety Systems 

      Oh, Jiyong; Golay, Michael W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2008-02)
      Passive cooling systems sometimes use natural circulation, and they are not dependent on offsite or emergency AC power, which can simplify designs through the reduction of emergency power supplying infrastructure. 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). ...

    • Modular Pebble Bed Reactor 

      Kadak, Andrew C.; Ballinger, Ronald G.; Driscoll, Michael J.; Yip, Sidney; Wilson, David Gordon; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-07)
      This project is developing a fundamental conceptual design for a gas-cooled, modular, pebble bed reactor. Key technology areas associated with this design are being investigated which intend to address issues concerning ...

    • 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 ...

    • Nuclear Energy for Simultaneous Low-Carbon Heavy-Oil Recovery and Gigawatt-Year Heat Storage for Peak Electricity Production 

      Forsberg, Charles W.; Krentz-Wee, Rebecca E.; Lee, You Ho; Oloyede, Isaiah O. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2010-12)
      In a carbon-constrained world or a world of high natural gas prices, the use of fossil-fueled power plants to satisfy variable electricity demands may be limited. Nuclear power plants operating at full capacity with ...

    • Nuclear Energy for Variable Electricity and Liquid Fuels Production: Integrating Nuclear with Renewables, Fossil Fuels, and Biomass for a Low- Carbon World 

      Forsberg, Charles W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-09)
      The world faces two energy challenges: (1) the national security and economic challenge of dependence on foreign oil and (2) the need to reduce carbon dioxide emissions from the burning of fossil fuels to avoid climate ...

    • 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 ...

    • Nuclear Tanker Producing Liquid Fuels From Air and Water: Applicable Technology for Land-Based Future Production of Commercial Liquid Fuels 

      Galle-Bishop, John Michael; Driscoll, Michael J.; Forsberg, Charles W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-06-01)
      Emerging technologies in CO[subscript 2] air capture, high temperature electrolysis, microchannel catalytic conversion, and Generation IV reactor plant systems have the potential to create a shipboard liquid fuel production ...

    • Nuclear-Renewables Energy System for Hydrogen and Electricity Production 

      Haratyk, Geoffrey; Forsberg, Charles W.; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-06-01)
      Climate change concerns and expensive oil call for a different mix of energy technologies. Nuclear and renewables attract attention because of their ability to produce electricity while cutting carbon emissions. However ...

    • ON THE USE OF THORIUM IN LIGHT WATER REACTORS 

      Kazimi, Mujid S.; Czerwinski, Kenneth R.; Driscoll, Michael J.; Hejzla, P.; Meyer, J. E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 1999-04)
      The advantages and disadvantages of the use of thorium bearing fuel in light water reactors have been examined several times from the beginning of the nuclear energy era until the late seventies. The recent motivation ...

    • OPTIMIZATION OF THE HYBRID SULFUR CYCLE FOR HYDROGEN GENERATION 

      Jeong, Y. H.; Kazimi, Mujid S.; Hohnholt, K. J.; Yildiz, Bilge (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2005-05-01)
      The hybrid sulfur cycle (modified from the Westinghouse Cycle) for decomposing water into oxygen and hydrogen is evaluated. Hydrogen is produced by electrolysis of sulfur dioxide and water mixture at low temperature, ...

    • 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 ...