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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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  • 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 ...
  • 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 ...
  • 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 ...
  • Johnson, Brian C.; Apostolakis, George E. (Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
    Sodium cooled fast reactors (SFRs) are considered as a novel example to exercise the Technology Neutral Framework (TNF) proposed in NUREG-1860. One reason for considering SFRs is that they have historically had a licensing ...
  • 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 ...
  • 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 ...
  • 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 ...
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