Published April 1, 1979 | Version v1
Miscellaneous

REDIFFUSION, 1-D Neutron Removal-Diffusion and Gamma Point-Kernel Calculation for Shielding

  • 1. United Kingdom Atomic Energy Authority, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)

Description

1 - Nature of physical problem solved: One-dimensional neutron and gamma-ray shield penetration calculations. For neutrons the removal- diffusion method is used. For gamma-rays there is the option of using either kernel integration with build-up factors or diffusion theory with a first flight correction. Linked calculations are possible in which the gamma-ray sources are calculated from the neutron fluxes. Neutron reaction-rates and gamma-ray dose and heating rates may be printed out. A detailed description of the different modules is included (MINNIE, NADCON, BADCON, REMOVAL, SCRIM, SREM, PARAMETERS, REGROUP, DIFFUSION, DOCTOR, GAMSOURCE, GRAB, MIXGAM, REMTWO..). 2 - Method of solution: The removal or un-collided fluxes from slab sources are fitted by sums of exponentials. For the gamma-ray first flight calculation these exponentials are evaluated by solving the diffusion equation with appropriate parameters. The diffusion equation is solved by a finite difference method. 3 - Restrictions on the complexity of the problem: There are no restrictions on individual magnitudes. Dynamic storage allocation is used, and the total storage available is easily changed to accommodate different problem sizes

Availability note (English)

Available on-line: http://www.nea.fr/abs/html/nea-0519.html

Additional details

Publishing Information

Imprint Pagination
[html]

Optional Information

Notes
1 ref.