  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.
