A perturbation method based on the Variational Nodal Method (VNM) of solving the neutron transport equation is developed for three-dimensional Cartesian geometry. The method utilizes the solution of the corresponding adjoint transport equation to calculate changes in the critical eigenvalue due to changes in cross sections. Both first order and exact perturbation theory expressions are derived. The adjoint solution algorithm has been formulated and incorporated into the VNM option of the Argonne National Laboratory DEF3D production code. The perturbation method is currently implemented as a post-processor to the VNM option of the DIF3D code. To demonstrate the efficacy of the method, example perturbations are applied to the Takeda Benchmark...
In this work, a solution for a two-dimensional neutron transport problem, in cartesian geometry, is ...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
The simplified spherical harmonics (SP{sub N}) method has been used as an approximation to the trans...
The perturbation source method (PSM), which is a Monte Carlo perturbation calculation method, is app...
The objective of this project has been to develop computational methods that will enable more effect...
This paper summarizes current progress and developments with the variational nodal method(VNM) and i...
In this research the singular perturbation technique is used to solve the one-dimensional neutron tr...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The development of the variational nodal method contained in the three-dimensional transport code VA...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
For a quick and accurate calculation of spatial neutron distribution in nuclear power reactors 3D no...
SIGLEAvailable from British Library Document Supply Centre- DSC:D36693/81 / BLDSC - British Library ...
In this work, a solution for a two-dimensional neutron transport problem, in cartesian geometry, is ...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...
The simplified spherical harmonics (SP{sub N}) method has been used as an approximation to the trans...
The perturbation source method (PSM), which is a Monte Carlo perturbation calculation method, is app...
The objective of this project has been to develop computational methods that will enable more effect...
This paper summarizes current progress and developments with the variational nodal method(VNM) and i...
In this research the singular perturbation technique is used to solve the one-dimensional neutron tr...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The development of the variational nodal method contained in the three-dimensional transport code VA...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
For a quick and accurate calculation of spatial neutron distribution in nuclear power reactors 3D no...
SIGLEAvailable from British Library Document Supply Centre- DSC:D36693/81 / BLDSC - British Library ...
In this work, a solution for a two-dimensional neutron transport problem, in cartesian geometry, is ...
Adaptive grid refinement strategies have been formulated to solve the even parity Boltzmann transpor...
"July 1972."VitaAlso written by the first author as a Ph. D. thesis, MIT, Dept. of Nuclear Engineeri...