Variational coarse mesh techniques are developed for the solution of the one group neutron transport equation in one-dimensional reactor lattices. In contrast to conventional nodal lattice applications which discretize diffusion theory and use node homogenized cross sections, we retain the spatial dependence of the cross sections and instead employ an alternative flux representation. The initial form of this flux representation (trial function) for the angular flux was inspired by the leading order solution in the asymptotic expansion of the angular flux--namely, the slow modulation of a periodic pin cell flux. We called the variational technique based on this form of trial function the Spectral Element Asymptotic Method (SEAM) and demonstr...
Equivalent cross sections used in few-group nodal diffusion calculations are ob- tained through homo...
Vita.Angular singularities for the multigroup neutron diffusion equation are examined. Since the sol...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
This paper is the second part of an investigation on the use of the spectral element method (sem) to...
A coarse mesh approximation method is presented for the solution of the two-dimensional spatial neut...
This paper is the second part of an investigation on the use of the spectral element method (SEM) to...
The finite element response matrix method has been applied to the solution of the neutron transport ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
Nodal diffusion is currently the preferred neutronics model for industrial reactor core calculations...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
Angular approximation techniques to the Boltzmann transport equation have been developed that are ac...
This paper discusses the application of the Legendre spectral element method to the steady one-veloc...
Equivalent cross sections used in few-group nodal diffusion calculations are ob- tained through homo...
Vita.Angular singularities for the multigroup neutron diffusion equation are examined. Since the sol...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
This paper is the second part of an investigation on the use of the spectral element method (sem) to...
A coarse mesh approximation method is presented for the solution of the two-dimensional spatial neut...
This paper is the second part of an investigation on the use of the spectral element method (SEM) to...
The finite element response matrix method has been applied to the solution of the neutron transport ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
Nodal diffusion is currently the preferred neutronics model for industrial reactor core calculations...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...
Angular approximation techniques to the Boltzmann transport equation have been developed that are ac...
This paper discusses the application of the Legendre spectral element method to the steady one-veloc...
Equivalent cross sections used in few-group nodal diffusion calculations are ob- tained through homo...
Vita.Angular singularities for the multigroup neutron diffusion equation are examined. Since the sol...
The spectral element method can be used to deal with the spatial operators of neutron transport prob...