BENDIX G-20 COMPUTER PROGRAMS FOR USE IN REACTOR SHIELD DESIGN

Technical Report · Sat Dec 01 04:00:00 EST 1962

OSTI ID:4736256

Fowler, A G

A series of six programs has been writien for the Bendix G-20 computer to calculate the neutron and gamma ray attenuation in a multi-region shield of a power reactor. This report gives the basic theory on which the programs are based as well as the input and operating instructions for the programs. The dose rate in the outer region of a reactor shield is due almost entirely to capture gamma rays produced locally. The thermal neutron flux, which is responsible for most of the capture gamma rays, is in general proportional to the number of fast neutrons slowed down in the immediate vicinity. Thus, to predict dose rate, it is essential to know the spatial and energy distribution of neutrons and gamma rays in the shield. The highenergy fission neutrons are treated using removal theory, and the slowing-down and thermal neutrons are treated using multi-group diffusion theory. The thermal neutrons produce capture gamma rays and the attenuation of these gammas is then calculated. (auth)

• Research Organization: Atomic Energy of Canada Ltd., Chalk River, Ont.
• NSA Number: NSA-17-013665
• OSTI ID: 4736256
• Report Number(s): CRRP-1127; AECL-1678
• Country of Publication: Canada
• Language: English

Related Subjects

ABSORPTION
ATTENUATION
CAPTURE
COMPUTERS
CONFIGURATION
DIFFUSION
ENERGY
FAST NEUTRONS
FISSION
GAMMA RADIATION
NEUTRON FLUX
NEUTRONS
NUCLEAR REACTIONS
OPERATION
PHYSICS
PLANNING
PROGRAMMING
RADIATION DOSES
REACTORS
SHIELDING
SLOWDOWN
SPECTRA
THERMAL NEUTRONS