Neutron source characterization and radiation damage calculations for material studies
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Abstract
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OpenAlex topics: Nuclear Materials and Properties · Nuclear Physics and Applications · Nuclear reactor physics and engineering
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References (13)
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8. Status of Neutron Cross Sections for Reactor Dosimetry
9. Routti · Computer Phys. Commun. · 1980 · 21 · 11910.1016/0010-4655(80)90081-8 ↗
10. Lindhard · Mat. Phys. Medd. Dan Vid Selsk. · 1963 · 33 · 14
11. Odette · Nucl. Technol. · 1976 · 29 · 34610.13182/NT76-A31600 ↗
12. Line and Continuum Gamma-Ray Yields from Thermal-Neutron Capture in 75 Elements
13. Descripton of Neutron Capture and Beta-Decay Processes Leading to Displacement Production