Graduation date: 1983Spatial flux profiles were calculated in idealized,\ud optically-thin ( 1 mfp) cell systems using integral\ud transport theory. Numerical accuracy improvement and\ud convergence efficiency in computing these spatial flux\ud profiles was the primary concern. Toward these ends, kernel\ud volume-averaging techniques for curvilinear cell systems, a\ud reflective angular-dependent edge source boundary condition\ud for optically-thin cell systems and an iterative heuristic\ud convergence method were developed.\ud To the optically-thin cell systems (slab, cylindrical,\ud and spherical), an angular-dependent edge source boundary\ud condition (equivalent to a Double-PN (PNN) boundary\ud condition) was applied to improve the flux...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
The main goal of the thesis is the proposition of highly accurate curved boundary conditions aiming ...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
Reported DSN calculations of reactivity worths of heterogeneities in ZPR- III fast critical assembli...
In solving the neutron diffusion equation in one cell of an infinite lattice, a common procedure is ...
In calculating a closely packed lattice, it is well known that one-velocity integral transport theor...
Within this article, current coupling collision probability method with expansion of flux by orthogo...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
In a recent article (Larsen, Morel, and Miller, J. Comput. Phys. 69, 283 (1987)), a theoretical meth...
Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (ND...
The influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Funding: UK EPSRC grant no. EP/N014642/1.We consider a continuum mechanical model of cell invasion t...
In this paper, we apply a special finite-volume scheme, limited to smooth temperature distributions ...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
The main goal of the thesis is the proposition of highly accurate curved boundary conditions aiming ...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
Reported DSN calculations of reactivity worths of heterogeneities in ZPR- III fast critical assembli...
In solving the neutron diffusion equation in one cell of an infinite lattice, a common procedure is ...
In calculating a closely packed lattice, it is well known that one-velocity integral transport theor...
Within this article, current coupling collision probability method with expansion of flux by orthogo...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
In a recent article (Larsen, Morel, and Miller, J. Comput. Phys. 69, 283 (1987)), a theoretical meth...
Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (ND...
The influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Funding: UK EPSRC grant no. EP/N014642/1.We consider a continuum mechanical model of cell invasion t...
In this paper, we apply a special finite-volume scheme, limited to smooth temperature distributions ...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
The main goal of the thesis is the proposition of highly accurate curved boundary conditions aiming ...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...