Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

TECHNIQUES FOR CALCULATING THE PENETRATION OF RADIATION IN DUCTS AND VOIDS.

Technical Report ·
OSTI ID:4831639
The performance of a power reactor shield is largely controlled by radiation which streams through the various penetrations associated with coolant circuits, refuelling channels, control mechanisms and services etc. A variety of methods for treating these problems has been discussed in the literature ranging from simple line-of-sight techniques to full-scall Monte Carlo calculations with more or less exact representations of the geometry. For simplicity, most design codes employ the albedo concept to predict the build-up of neutrons due to multiple scattering at the walls. In the duct systems associated with the gas-cooled graphite reactors which have been devleoped in the U.K. Power Programme, however, the efficiency of anti-streaming steps or bends is reduced by radiation which penetrates directly through the walls from the surrounding material. This phenonenon is less important in ducts passing through shields composed of water or concrete, which are more frequently discussed in the published literature. The capabilities of simple line-of-sight analysis, albedo and Monte Carlo techniques under these conditions have been investigated by comparing predictions with measurements made in various ducts and slot configurations set up in the LIDO and GLEEP experimental facilities. Consideration is also given to the problem of calculating the neturon flux penetraing the lattice of gas-filled channels which constitutes the charge-face reflector of graphite-moderated power reactors. The accuracy of the simple design techniques which are used for predicting the sources of neutron streaming within the charge-face shields of Magnox and A.G.R. systems is established by comparing predictions with both Monte Carlo calculations, and experiments on the axial reflectors of GLEEP and the zero-energy reactor HERO at Windscale.
Research Organization:
Atomic Energy Establishment, Winfrith (England)
NSA Number:
NSA-23-013463
OSTI ID:
4831639
Report Number(s):
AERE-R--5773(Vol.3)
Country of Publication:
United Kingdom
Language:
English