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

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

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  • 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 ...
  • Herman, Bryan R.; Shwageraus, Eugene; Forget, Benoit; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
    High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to achieve a conversion ratio of ...
  • 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 ...
  • Bates, Ethan A.; Buongiorno, Jacopo; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
    Disposal of high-level nuclear waste in deep boreholes drilled into crystalline bedrock (i.e., “granite”) is an interesting repository alternative of long standing. Work at MIT over the past two decades, and more recently ...
  • Kazimi, Mujid S.; Dobisesky, J.; Carpenter, David M.; Richards, J.; Pilat, Edward E.; Shwageraus, Evgeni (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-04)
    The use in present generation PWRs of fuel clad with silicon carbide rather than Zircaloy has been evaluated as an aid to reaching higher discharge burnups and to operation at higher reactor power levels. A preliminary ...
  • 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 ...
  • Jensen, K. G.; Driscoll, Michael J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-07)
    This is a progress report covering work through July 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. The ...
  • Driscoll, Michael J.; Jensen, K. G. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-05-01)
    This is a progress report covering work through mid-May 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 ...
  • Conboy, Thomas M.; McKrell, Thomas J.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-05)
    In order to significantly increase the power density of Light Water Reactors (LWRs), the helical-cruciform (HC) fuel rod assembly has been proposed as an alternative to traditional fuel geometry. The HC assembly is a ...
  • 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 ...
  • Holcombe, Robert; Golay, Michael W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-04)
    Nuclear Proliferation is a complex problem that has plagued national security strategists since the advent of the first nuclear weapons. As the cost to produce nuclear weapons has continued to decline and the availability ...
  • 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. ...
  • Sapiie, B.; Driscoll, Michael J.; Jensen, K. G. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-01)
    This report develops and exercises broad-area site selection criteria for deep boreholes suitable for disposal of spent nuclear fuel and/or its separated constituents. Three candidates are examined: a regional site in the ...
  • 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 ...
  • 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 ...
  • Guérin, Laurent; Feng, Bo; Hejzlar, Pavel; Forget, Benoit; Kazimi, Mujid S.; Van Den Durpel, Luc; Yacout, Abdellatif; Taiwo, Temi; Dixon, Brent W.; Matthern, Grechen; Boucher, Lionel; Delpech, Marc; Girieud, Richard; Meyer, Maryan (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-04)
    As use of nuclear energy is expected to expand in different parts of the world, several codes that describe the nuclear fuel cycle system are currently under development, featuring a range of capabilities and different ...
  • 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 ...
  • 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 ...
  • Todreas, Neil E.; Hejzlar, Pavel; Fong, Chris J.; Nikiforova, Anna; Petroski, Robert; Shwageraus, Eugene; Whitman, Joshua (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 ...
  • 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 ...
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