Litcius/Paper detail

Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR

Shôji Nakamura, Yuji Shibahara, Shunsuke Endo, Atsushi Kimura

2021Journal of Nuclear Science and Technology16 citationsDOI

Abstract

Using an activation method with a well-thermalized neutron field, it is principally possible to drive a thermal-neutron capture cross-section without considering an epithermal neutron component. We demonstrated neutron capture cross-section measurements using the graphite thermal column (TC-Pn) of the Kyoto University Research Reactor. First, in order to confirm that the graphite thermal column was a well-thermalized neutron field, neutron irradiation was performed with neutron flux monitors: 197Au, 59Co, 45Sc, 63Cu, and 98Mo. The TC-Pn was confirmed to be extremely thermalized on the basis of Westcott’s convention, because the thermal-neutron flux component took a constant value regardless of the sensitivity of each flux monitor to epithermal neutrons. Next, as a demonstration, the thermal-neutron capture cross-section of 181Ta(n,γ)182m+gTa reaction was measured using the graphite thermal column, and then derived to be 20.5 ± 0.4 barn, which supported the evaluated value of 20.4 ± 0.3 barn. The 181Ta nuclide could be useful as a flux monitor that complements the sensitivity between 197Au and 98Mo monitors.

Topics & Concepts

Neutron temperatureNeutron fluxNeutron cross sectionNeutronGraphiteResearch reactorNeutron captureRadiochemistryNeutron moderatorNeutron activationTantalumNuclear physicsMaterials scienceChemistryAnalytical Chemistry (journal)PhysicsComposite materialMetallurgyChromatographyNuclear Physics and ApplicationsNuclear reactor physics and engineeringRadiation Detection and Scintillator Technologies