Add to ORKGThesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979.MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE.Includes bibliographical references.by Kord S. Smith.Nucl.E
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
172 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The multigroup neutron diffus...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
The nodal methods are significantly more accurate than the traditional methods such as finite differ...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
The overall objective of this thesis is to develop an economical computational method for multidimen...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE ...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The feasibility and practical implementation of axial expansion methods for the solution of the mult...
Thesis. 1977. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.MICROFICHE ...
The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal me...
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
Abstract. The distribution of neutron population in nuclear reactor is described by using transport ...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
172 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The multigroup neutron diffus...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
The nodal methods are significantly more accurate than the traditional methods such as finite differ...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
The overall objective of this thesis is to develop an economical computational method for multidimen...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE ...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The feasibility and practical implementation of axial expansion methods for the solution of the mult...
Thesis. 1977. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.MICROFICHE ...
The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal me...
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
Abstract. The distribution of neutron population in nuclear reactor is described by using transport ...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
172 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The multigroup neutron diffus...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...