DOE-HDBK-1019/1-93Reactor Theory (Neutron Characteristics)NUCLEAR CROSS SECTIONS AND NEUTRON FLUXRev. 0Page 5NP-02NUCLEAR CROSS SECTIONS AND NEUTRON FLUXTo determine the frequency of neutron interactions, it is necessary to describe theavailability of neutrons to cause interaction and the probability of a neutroninteracting with material. The availability of neutrons and the probability ofinteraction are quantified by the neutron flux and nuclear cross section.EO 2.1DEFINE the following terms:a.Atom densityd.Barnb.Neutron fluxe.Macroscopic cross sectionc.Microscopic cross sectionf.Mean free pathEO 2.2EXPRESS macroscopic cross section in terms of microscopic crosssection.EO 2.3DESCRIBE how the absorption cross section of typical nuclidesvaries with neutron energy at energies below the resonanceabsorption region.EO 2.4DESCRIBE the cause of resonance absorption in terms of nuclearenergy levels.EO 2.5DESCRIBE the energy dependence of resonance absorption peaksfor typical light and heavy nuclei.EO 2.6EXPRESS mean free path in terms of macroscopic cross section.EO 2.7Given the number densities (or total density and componentfractions) and microscopic cross sections of components,CALCULATE the macroscopic cross section for a mixture. EO 2.8CALCULATE a macroscopic cross section given a material density,atomic mass, and microscopic cross section.EO 2.9EXPLAIN neutron shadowing or self-shielding.
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