Browsing Nuclear Fuel Cycle Technology and Policy Program (NFC) - Technical Reports by Title

Now showing items 11-30 of 45

    • Experimental Determination of Thermal Conductivity of a Lead- Bismuth, Eutectic-Filled Annulus 

      Carpenter, David M.; Kohse, Gordon E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-06)
      In order to obtain an accurate prediction of the thermal behavior of an annular fuel assembly (see MIT-NFC-PR-048 for a description of the rods), the thermal conduction of the region from the outside of the fuel capsule ...

    • Feasibility of Breeding in Hard Spectrum Boiling Water Reactors with Oxide and Nitride Fuels 

      Feng, Bo; Kazimi, Mujid S.; Forget, Benoit (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06-01)
      This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using the higher density nitride fuel ...

    • Feasibility of Partial ZrO[subscript 2] Coatings on Outer Surface of Annular UO[subscript 2] Pellets to Control Gap Conductance 

      Feinroth, H.; Yuan, Y. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-06)
      The viability of depositing a thin porous coating of zirconia on the outer surface of an annular UO[subscript 2] pellet is investigated experimentally. Such a layer has been proposed to buffer the contact between the fuel ...

    • Feasibility of Very Deep Borehole Disposal of US Nuclear Defense Wastes 

      Dozier, Frances E.; Driscoll, Michael J.; Buongiorno, Jacopo (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
      This report analyzes the feasibility of emplacing DOE-owned defense nuclear waste from weapons production into a permanent borehole repository drilled ~4 km into granite basement rock. Two canister options were analyzed ...

    • Flexible Conversion Ratio Fast Reactor Systems Evaluation Final Report 

      Todreas, Neil E.; Hejzlar, Pavel; Fong, Chris J.; Nikiforova, Anna; Petroski, Robert; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-06)
      Executive Summary: The goal of this project is to develop the conceptual designs of fast flexible conversion ratio reactors using lead and liquid salt coolants and to compare the results with a gascooled fast reactor ...

    • A Framework for Performance Assessment and Licensing of Deep Borehole Repositories 

      Jensen, K. G.; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-03)
      This is the initial progress report under a Sandia-MIT contract dealing with development of engineering and geological siting criteria for deep borehole disposal of spent nuclear fuel or its separated constituents. ...

    • Fuel Cycle Options for Optimized Recycling of Nuclear Fuel 

      Aquien, A.; Kazimi, Mujid S.; Hejzlar, Pavel (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-06)
      The reduction of transuranic inventories of spent nuclear fuel depends upon the deployment of advanced fuels that can be loaded with recycled transuranics (TRU), and the availability of facilities to separate and reprocess ...

    • FUEL PERFORMANCE ANALYSIS OF EXTENDED OPERATING CYCLES IN EXISTING LWRs 

      Handwerk, C. S.; Meyer, J. E.; Todreas, Neil E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 1998-01)
      An integral part of a technical analysis of a core design, fuel performance is especially important for extended operating cycles since the consequences of failed fuel are greater for this operating strategy than for ...

    • A Generalized Optimization Methodology for Isotope Management 

      Massie, Mark Edward; Forget, Benoit (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-09)
      This research focuses on developing a new approach to studying the nuclear fuel cycle: instead of employing the trial and error approach currently used in actinide management studies in which reactors are designed and ...

    • 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 ...

    • 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 ...

    • 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: 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 ...

    • High Performance Fuel Design for Next Generation PWRs: Final Report 

      Kazimi, Mujid S.; Hejzlar, Pavel; Carpenter, David M.; Feng, Dandong; Kohse, Gordon E.; e.a. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-01)
      This summary provides an overview of the results of the U.S. DOE funded NERI (Nuclear Research Energy Initiative) program on development of the internally and externally cooled annular fuel for high power density PWRs. ...

    • HLW Deep Borehole Design and Assessment: Notes on Technical Performance 

      Jensen, K. G.; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-04-01)
      This is a progress report covering work through mid-April 2010 under a Sandia-MIT contract dealing with design and siting/licensing criteria for deep borehole disposal of spent nuclear fuel or its separated constituents. It ...

    • 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 ...

    • 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 ...

    • 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). ...

    • 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 ...