Analysis of Neutron Streaming Experiment for Torus Duct by Cf-252 Neutron Source

Abstract

The neutron streaming for torus duct was investigated experimentally and analytically by using actual scale of experimental setups and 252 Cfneutron source, in order to obtain the basic data of the shielding design such as the nuclear fuel facilities. The torus ducts with 1 m of radius of curvature and 3cm and 5cm of the duct diameters were used. Neutron doses were measured by REM counter and solid state track detector (SSTD). The MCNP4A calculation was done for the comparison with the experimental results. In the case where the arrangement of the source and the detector is comparatively able to foresee through the duct, the doses were high as a matter of course. In the case where the other side could not be foreseen directly through the torus duct, the dose became 4E-2 as compared with the straight duct. The dose for 3 cm of the duct diameter was generally smaller than that of 5 cm. The doses for 3cm increased only 7% as compared with the bulk case (90 cm thickness, source position: disk, detector position: center).