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The measurement of the 15N(n,n) total and scattering cross section

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DataCite Commons2026-03-18 更新2026-05-05 收录
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https://topcat.isis.stfc.ac.uk/doi/INVESTIGATION/136276661/
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To date, nitrogen has not been used in commercial reactor fleets as a major constituent of fuel or other significant material, and significant uncertainties surrounding its expected performance. Reactor modelling, neutronics calculations and burn-up predictions are heavily reliant on the underlying nuclear data for nitrogen (neutron cross sections), and these data have been shown to have a significant effect on key predicted quantities such as reactor criticality. The less abundant 15N is present at 0.38% levels naturally and has more favourable neutron absorption cross sections; the total thermal absorption cross section is ∼25 µb. For this reason, a measurement of the 15N(n,n) total and scattering cross section is proposed using the VESUVIO neutron spectrometer in the standard configuration.
提供机构:
ISIS Facility
创建时间:
2026-03-18
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