Removal cross sections for 14.6 MeV neutrons |
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Authors: | P. Fuga |
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Affiliation: | (1) Institute of Nuclear Physics Tirana, (Albania) |
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Abstract: | This paper reports on the determination of removal cross sections for different materials as paraffin, lead, graphite, concrete, and wood. The experimentally determined values of removal cross sections concerning these materials are respectively: 0.072±0.001, 0.089±0.003, 0.067±0.006, 0.071±0.003 and 0.0360±0.0005 cm–1. |
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