Fast-Neutron Transport in Shields Having Limited Transverse Dimensions,
FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OHIO
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In this paper the authors discuss results of experiments on the spatial, angular, and energy distributions of a fast-neutron flux in cylindrical specimens made of boron carbide, lithium hydride, aluminum, iron, and lead.
- Nuclear Radiation Shielding, Protection and Safety
- Nuclear Physics and Elementary Particle Physics