Determination of Buildup Factors in Titanium and Depleted Uranium*

Year
1995
Author(s)
T.H. Jones - University of New Mexico
R.D. Busch - University of New Mexico
J.A. Miller - University of New Mexico
K.D. Seager - Sandia National Laboratories, USA
File Attachment
1224.PDF2.13 MB
Abstract
Approximately 13% by volume of the U.S. Department of Energy (DOE) current backlog of radioactive waste is characterized as high-level waste. Transportation of these wastes requires that the waste package have adequate shielding against gamma radiation. This project investigates the radiation shielding performance of titanium and depleted uranium, which have been proposed for use as gamma-shielding materials in DOE transportation packages, by experimentally determining their buildup factors. Buildup factors are important in shield heating and radiation damage calculations. A point-isotropic-source type of buildup factor is the most useful for application in the point-kernel approach utilized in many simple shielding codes. The point-kernel method provides reasonable results for cases in which the shield is made of one solid material and the source can be approximated as one homogeneous material. The point-kernel method has been incorporated into a large number of shielding codes treating three-dimensional geometry using buildup factor data in some form. Buildup factors vary with a number of parameters such as the distance of penetration through the attenuating medium; the geometric configuration of the attenuating medium, source, and detector position; the composition of the medium; the detector response function; and the energy and direction of emission of the source photons, ideally taken to be monoenergetic and isotropic.