Author: M. L. Tobias
Publisher:
ISBN:
Category : Diffusion processes
Languages : en
Pages : 46
Book Description
The Twenty Grand Program for the Numerical Solution of Few-group Neutron Diffusion Equations in Two Dimensions
Author: M. L. Tobias
Publisher:
ISBN:
Category : Diffusion processes
Languages : en
Pages : 46
Book Description
Publisher:
ISBN:
Category : Diffusion processes
Languages : en
Pages : 46
Book Description
The Twenty Grand Program for the Numerical Solution of Few-Group Neutron Diffusion Equations in Two Dimensions
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are available. Normalization of fluxes to an arbitrary input power is allowed. The fission source distribution and the adjoint fluxes and associated integrals may be computed at the user's option. The number of mesh sweeps permitted is stated as input. The average running time in seconds per iteration per group is approximately 0.0035. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are available. Normalization of fluxes to an arbitrary input power is allowed. The fission source distribution and the adjoint fluxes and associated integrals may be computed at the user's option. The number of mesh sweeps permitted is stated as input. The average running time in seconds per iteration per group is approximately 0.0035. (auth).
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1090
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1090
Book Description
The KAK program for the numerical solution of few group neutron diffusion equations in two dimensions
Author: Nihon Genshiryoku Kenkyūjo
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Intense Neutron Sources
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 856
Book Description
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 856
Book Description
Nuclear Science and Engineering
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 602
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 602
Book Description
Computational Methods in Engineering and Science
Author: Shoichiro Nakamura
Publisher:
ISBN:
Category : Differential equations
Languages : en
Pages : 488
Book Description
Publisher:
ISBN:
Category : Differential equations
Languages : en
Pages : 488
Book Description
Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory
Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 256
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 256
Book Description
STREAK, a Numerical Solution for Space-time Neutron Diffusion Equations
Author: James W. Smiley
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 70
Book Description
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 70
Book Description
Engineering Manual
Author: Robert H. Perry
Publisher:
ISBN:
Category : Engineering
Languages : en
Pages : 810
Book Description
Publisher:
ISBN:
Category : Engineering
Languages : en
Pages : 810
Book Description