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

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

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  • 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 ...
  • Marchinkowski, K.; Weil, R.; Apostolakis, G. A. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2000-04)
  • Marchinkowski, K.; Weil, R.; Apostolakis, George E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2000-04)
    1. Overview 1.1 Introduction to the CATILaC Methodology By understanding the way that a facility coordinates the work it does, failure events can be placed into a broader organizational context. Once the organizational ...
  • 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 ...
  • Galen, T. A.; Wilson, D. G.; Kadak, A. C. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-02)
    A comparison between air and helium for use as working fluids in the energy-conversion cycle of the MPBR is presented. To date, helium has been selected in the MPBR indirect-cycle working reference design. Air open- and ...
  • Hejzlar, P.; Todreas, N. E.; Driscoll, M. J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1994-06)
    A design for a large, passive, light water reactor has been developed. The proposed concept is a pressure tube reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid SiC-coated ...
  • Hejzlar, P.; Todreas, N. E.; Driscoll, M. J. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 1994-06-01)
    A design for a large, passive, light water reactor has been developed. The proposed concept is a pressure tube reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid Sic-coated ...
  • Buongiorno, J.; Todreas, N. E; Kazimi, Mujid S.; Czerwinski, K. R. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2001-03)
    The feasibility of a lead-bismuth (Pb-Bi) cooled fast reactor that eliminates the need for steam generators and coolant pumps was explored. The working steam is generated by direct contact vaporization of water and liquid ...
  • Ko, Yu-Chih; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-10)
    The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron ...
  • Bean, Malcolm K.; Dewitt, Gregory Lee; Cabeche, Dion T.; Gerrity, Thomas P.; Haratyk, Geoffrey; Kersting, Alyssa R.; Lee, Youho; Virgen, Matthew M.; Lenci, Giancarlo; Lin, Christie; Metzler, Florian; Ochoukov, Roman Igorevitch; Reed, Mark; Sobes, Vladimir; Sugrue, Rosemary M.; Shwageraus, Eugene; Wisniowska, Agata Elzbieta; Youchak, Paul M. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-08-01)
    Molten salt is a promising coolant candidate for Advanced High Temperature Reactor (AHTR) Gen-IV designs. The low neutron absorption, high thermal capacity, chemical inertness, and high boiling point at low pressure of ...
  • Lee, Youho; Forsberg, Charles W. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-06)
    Nuclear plants have high capital costs and low operating costs that favor base-load operation. This characteristic of nuclear power has been a critical constraint that limits the portion of nuclear power plants in a grid ...
  • Hejzlar, Pavel; Driscoll, Michael J.; Kazimi, Mujid S. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-02)
    Destruction of actinides in accelerator-driven subcriticals and in stand-alone critical reactors is of contemporary interest as a means to reduce long-term high-level waste radiotoxicity. This topical report is focused ...
  • Truong, Bao H.; Hu, Lin-Wen; Buongiorno, Jacopo (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2008-06)
    Nanofluids are engineered colloidal dispersions of nanoparticles (1-100nm) in common fluids (water, refrigerants, or ethanol…). Materials used for nanoparticles include chemically stable metals (e.g., gold, silver, ...
  • 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 ...
  • 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 ...
  • Kempf, Stephanie A.; Hu, Lin-Wen; Forget, Benoit (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-06-01)
    In response to increasing demands for the services of research reactors, a 5 MW LEUfueled research reactor core is developed and optimized to provide high thermal flux within specified limits upon thermal hydraulic ...
  • Short, Michael P.; Ballinger, Ronald G. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-10)
    A material that resists lead-bismuth eutectic (LBE) attack and retains its strength at 700°C would be an enabling technology for LBE-cooled reactors. No single alloy currently exists that can economically meet the required ...
  • Ellis, T.S.; Forget, Benoit; Kazimi, Mujid S.; Newton, T.; Pilat, Edward E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2009-02-01)
    Worldwide, there is limited test reactor capacity to perform the required irradiation experiments on advanced fast reactor materials and fuel designs. This is particularly true in the U.S., which no longer has an operating ...
  • 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 ...
  • Romano, Paul Kollath; Newton, Thomas H., Jr.; Forget, Benoit (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2009-06-01)
    Pursuant to a 1986 NRC ruling, the MIT Reactor (MITR) is planning on converting from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. Prior studies have shown that the MITR will be able ...
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