# Measurement of the $^{64}$Zn,$^{47}$Ti(n,p) Cross Sections using a DD Neutron Generator for Medical Isotope Studies

## TL;DR

This study measures specific neutron-induced reaction cross sections on zinc and titanium isotopes using a compact DD neutron generator, providing precise data relevant for medical isotope production.

## Contribution

It introduces a method for accurate cross section measurements using a flux-trap neutron generator, with results that improve precision over previous data.

## Key findings

- Measured $^{64}$Zn(n,p)$^{64}$Cu cross section as 46.4 ± 1.7 mb.
- Measured $^{47}$Ti(n,p)$^{47}$Sc cross section as 26.26 ± 0.82 mb.
- Results agree with existing data and theoretical models, with uncertainties below 5%.

## Abstract

Cross sections for the $^{47}$Ti(n,p)$^{47}$Sc and $^{64}$Zn(n,p)$^{64}$Cu reactions have been measured for quasi-monoenergetic DD neutrons produced by the UC Berkeley High Flux Neutron Generator (HFNG). The HFNG is a compact neutron generator designed as a "flux-trap" that maximizes the probability that a neutron will interact with a sample loaded into a specific, central location. The study was motivated by interest in the production of $^{47}$Sc and $^{64}$Cu as emerging medical isotopes. The cross sections were measured in ratio to the $^{113}$In(n,n')$^{113m}$In and $^{115}$In(n,n')$^{115m}$In inelastic scattering reactions on co-irradiated indium samples. Post-irradiation counting using an HPGe and LEPS detectors allowed for cross section determination to within 5% uncertainty. The $^{64}$Zn(n,p)$^{64}$Cu cross section for 2.76$^{+0.01}_{-0.02}$ MeV neutrons is reported as 49.3 $\pm$ 2.6 mb (relative to $^{113}$In) or 46.4 $\pm$ 1.7 mb (relative to $^{115}$In), and the $^{47}$Ti(n,p)$^{47}$Sc cross section is reported as 26.26 $\pm$ 0.82 mb. The measured cross sections are found to be in good agreement with existing measured values but with lower uncertainty (< 5%), and also in agreement with theoretical values. This work highlights the utility of compact, flux-trap DD-based neutron sources for nuclear data measurements and potentially the production of radionuclides for medical applications.