Measurements of neutron capture cross-sections for nuclides of interest in decommissioning: ⁴⁵ Sc, ⁶³ Cu, ⁶⁴ Zn, ¹⁰⁹ Ag, and ¹¹³ In

As nuclear facilities are dismantled in decommissioning, various and large amounts of waste are generated. Even more inconveniently, they are radioactive waste due to neutron activation. Thus, the neutron capture cross-sections of nuclides targeted for decommissioning are required to evaluate the radioactivity produced. The present study selected45Sc, 63Cu, 64Zn, 109Ag and113In among targeted nuclides, and performed the measurements of thermal-neutron capture cross-sections by an activation method at the Kyoto University Research Reactor. The thermal-neutron capture cross-sections were derived on the basis of Westcott's convention. The present results were obtained as follows: 27.18 ± 0.28 barn for45Sc(n,γ)46Sc, 4.34 ± 0.06 barn for63Cu(n,γ)64Cu, 0.719 ± 0.011 barn for64Zn(n,γ)65Zn, 4.05 ± 0.05 barn for109Ag(n,γ)110mAg and 8.53 ± 0.27 barn for113In(n,γ)114Inm1+m2 reactions. The results for45Sc and64Zn support evaluated cross-section data within the limits of uncertainties, while those for the other nuclides were slightly different from evaluated ones. The obtained results are useful not only for the evaluation of isotope production, but also for the consideration of those nuclides as flux monitors, as an alternative to Au and Co.