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The finite element method for neutron diffusion problems in hexagonal geometry
(Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975, 1975)
Finite element synthesis method
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975, 1975)
Description of the two-dimensional nodal codes "NRMS," a multigroup static code, and "NRMT," a one- and two-group transient code for solution of the neutron diffusion equation in rectangular geometry
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1977], 1977)
Spatial homogenization of diffusion theory parameters
(Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1977, 1977)
Spatially dependent velocities for the Gakin II reactor kinetics code
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1978, 1978)
A coarse-mesh nodal diffusion method based on response matrix considerations
(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 ...
Description of the computer code 2DTD
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976], 1976)
Variational derivation of modal-nodal finite difference equations in spatial reactor physics
(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 ...
Nonlinear methods for solving the diffusion equation
(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 ...
GAKIN II : a one-dimensional multigroup diffusion theory reactor kinetics code
([Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1973], 1973)