Methods for calculating approximate first collision probabilities for neutrons in cylindrical and cluster lattices are presented and compared with numerical solution methods. The methods differ from those of other authors in the inclusion of anisotropic boundary conditions for both geometries. The methods, which are fast enough for routine use in multigroup and resonance subgroup calculations, have been coded in FORTRAN and included in modules of the AUS scheme for reactor neutronics calculations
International audienceMany years have been devoted to study the behaviour of solids submitted to imp...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
The solution of neutron diffusion equation is important to describe the behavior of the neutrons in ...
Four methods for the calculation of multigroup collision probabilities in cluster geometry are descr...
Equations are presented for the calculation of collision probabilities in cylindrical geometry with ...
There the paper purposes are to evolve the probability method of first collisions for its effective ...
Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Camp...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
Neste trabalho, o método das probabilidades de colisão (método CP) é aplicado µa solução do problema...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
In many problems of reactor physics anisotropic scattering of neutrons in the high energy range has ...
Nuclear fuel cell calculation is one of the most complicated steps of neutron transport problems in ...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
International audienceMany years have been devoted to study the behaviour of solids submitted to imp...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
The solution of neutron diffusion equation is important to describe the behavior of the neutrons in ...
Four methods for the calculation of multigroup collision probabilities in cluster geometry are descr...
Equations are presented for the calculation of collision probabilities in cylindrical geometry with ...
There the paper purposes are to evolve the probability method of first collisions for its effective ...
Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Camp...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
Neste trabalho, o método das probabilidades de colisão (método CP) é aplicado µa solução do problema...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
In many problems of reactor physics anisotropic scattering of neutrons in the high energy range has ...
Nuclear fuel cell calculation is one of the most complicated steps of neutron transport problems in ...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
International audienceMany years have been devoted to study the behaviour of solids submitted to imp...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
The solution of neutron diffusion equation is important to describe the behavior of the neutrons in ...