Browsing Department of Nuclear Engineering by Author "Henry, Allan F."

Now showing items 1-7 of 7

    • A coarse-mesh nodal diffusion method based on response matrix considerations 

      Henry, Allan F.; Sims, Randal Nee (Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1977], 1977)
      The overall objective of this thesis is to develop an economical computational method for multidimensional transient analysis of nuclear power reactors. Specifically, the application of nodal methods based on the multigroup ...

    • A new approach to solving the multimode kinetics equations 

      Turnage, Joe Clayton; Henry, Allan F. ([Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1972], 1972)

    • Nonlinear methods for solving the diffusion equation 

      Shober, Robert Anthony; Henry, Allan F. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976], 1976)
      This thesis is concerned with methods for the transient solution of the neutron diffusion equations in one or two energy groups. Initially, nonlinear methods for solving the static diffusion equations using the finite ...

    • The Reactivity and transient analysis of MITR-II 

      Yarman, Nuh Tolga; Henry, Allan F.; Lanning, David D.; Gosnell, James Waterbury (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)
      The two-dimensional, time dependent, three-group diffusion equations for the proposed designed core of the MIT reactor are written with an extra source term accounting for the photoneutrons generated in the D20 reflector. ...

    • The replacement of reflectors by Albedo-type boundary conditions 

      Kalambokas, Panagiotis Constantinos; Henry, Allan F. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1975], 1975)
      The idea of the representation of reflectors by boundary conditions in static and dynamic reactor calculations is investigated. Analytical, group-diffusion theory boundary conditions relating neutron flux to normal current ...

    • Time integration methods for reactor kinetics 

      Nóbrega, José de Anchieta Wanderley da; Henry, Allan F. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [], )
      A technique based on the Padé approximations is applied to the solution of the point kinetics equations. The method consists of treating explicitly the roots of the inhour formula which would make the Padé approximations ...

    • Variational derivation of modal-nodal finite difference equations in spatial reactor physics 

      Bailey, Patrick Gage; Henry, Allan F. (Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)
      A class of consistent coarse mesh modal-nodal approximation methods is presented for the solution of the spatial neutron flux in multigroup diffusion theory. The methods are consistent in that they are systematically derived ...