Measurements of neutron capture cross-sections for nuclides of interest in decommissioning (IV): <sup>165</sup>Ho(n, γ)<sup>166m, 166g</sup>Ho reactions
During the decommissioning of nuclear facilities, large amounts of radioactive wastes are generated from structural materials. When considering the disposal or reuse of such wastes, accurate neutron capture cross-sections are required to evaluate the amounts of radioactive nuclides among the wastes. The present work selected <sup>165</sup>Ho among nuclides included in the list for clearance levels in decommissioning and measured the thermal-neutron capture cross-sections for the <sup>165</sup>Ho(n, γ)<sup>166m</sup>Ho, <sup>166g</sup>Ho reactions by the neutron activation method. The thermal cross-section measurements were performed with the graphite thermal column of the Kyoto University Research Reactor under the 5-MW operation and the thermal-neutron capture cross-sections were derived on the basis of <i>Westcott</i>’s convention. In this work, a value of 2.79 ± 0.04 barn was obtained for the <sup>165</sup>Ho(n,γ)<sup>166m</sup>Ho reaction, and 61.2 ± 0.6 barn for the <sup>165</sup>Ho(n,γ)<sup>166g</sup>Ho reaction. The combination of these cross-sections presented 64.0 ± 0.6 barn, which supports the recent evaluated data of 64.69 barn and 64.4 ± 1.2 barn within the limit of uncertainties.
Publication Details
- Journal
- Figshare
- Published
- 2025-01-01
- DOI
- https://doi.org/10.6084/m9.figshare.29410943
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 0.00