Browsing Dept. of Nuclear Engineering Technical Reports by Subject "Breeder reactors"

Now showing items 1-12 of 12

    • An accident probability analysis and design evaluation of the gas-cooled fast breeder reactor demonstration plant 

      De Laquil, Pascal; Lanning David D.; Rasmussen Norman C. (Cambridge, [Mass.] : Massachusetts Institute of Technology Dept. of Nuclear Engineering, 1976, 1976)

    • Analysis of mixing data relevant to wire wrapped fuel assembly thermal-hydraulic design 

      Ḵẖāṉ, Ahsānullāh; Todreas, Neil E.; Rohsenow, Warren M.; Sonin, A. A. (Cambridge, Mass. : Departments of Mechanical Engineering and Nuclear Engineering, Massachusetts Institute of Technology [1974], 1974)
      In this report analysis of recent experimental data is presented using the ENERGY code. A comparison of the accuracy of three types of experiments is also presented along with a discussion of uncertainties in utilizing ...

    • Assessment of thorium blankets for fast breeder reactors 

      Wood, Paul Joseph; Driscoll Michael J. (Cambridge, Mass. : Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1973, 1973)

    • Design, construction and evaluation of a facility for the simulation of fast reactor blankets 

      Forbes, Ian Alexander; Driscoll, Michael J.; Thompson, Theos Jardin, 1918-1970; Kaplan, Irving, 1912-; Manning, David D. (Cambridge, Mass. : Massachusetts Institute of Technology,  Dept. of Nuclear Engineering, [1970], 1970)
      A facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by ...

    • The effect of reactor size on the breeding economics of LMFBR blankets 

      Tagishi, Akinori; Driscoll, Michael J. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1975], 1975)
      The effect of reactor size on the neutronic and economic performance of LMFBR blankets driven by radially-power-flattened cores has been investigated using both simple models and state-of-the-art computer methods. Reactor ...

    • Evaluation of advanced fast reactor blanket designs 

      Shin, Jae In; Driscoll Michael J. (Cambridge, [Mass.] : Massachusetts Institute of Technology, 1977, 1977)

    • Evaluation of high performance LMFBR blanket configurations 

      Brown, Gilbert Jay; Driscoll, Michael J. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1974, 1974)

    • An evaluation of the fast-mixed spectrum reactor 

      Loh, Wee Tee; Driscoll, Michael J.; Lanning, David D. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1980], 1980)
      An independent evaluation of the neutronic characteristics of a gas-cooled fast-mixed spectrum reactor (FMSR) core design has been performed. A benchmark core configuration for an early FMSR design was provided by Brookhaven ...

    • Evaluation of the parfait blanket concept for fast breeder reactors 

      Ducat, Glenn Alexander; Driscoll, Michael J.; Todreas, Neil E. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1974], 1974)
      An evaluation of the neutronic, thermal-hydraulic, mechanical and economic characteristics of fast breeder reactor configurations containing an internal blanket has been performed. This design, called the parfait blanket ...

    • Gamma heating measurements in fast breeder reactor blankets 

      Scheinert, Paul Albert; Driscoll Michael J. (Cambridge, Mass. : Massachusetts Institute of Technology. Dept. of Nuclear Engineering, 1974, 1974)

    • Optimization of material distributions in fast breeder reactors 

      Tzanos, C. P.; Gyftopoulos E. P.; Driscoll Michael J. (Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971)

    • A Solid breeder tokamak blanket designed for failure mode operation 

      Chen, Franklin Fun Kun; Griffith, P. (Peter); McManamy, Thomas Joseph; Was, Gary S. (Gary Steven), 1953- (Cambridge, Mass. : Fusion Technology Program, Massachusetts Institute of Technology, 1977, 1977)
      The objective of this study was to evaluate a new concept for a Tokamak type fusion reactor blanket. The design was based on using a packed bed of lithium aluminate as the breeding material with helium gas cooling. The ...