Measurement of the $^{64}$Zn,$^{47}$Ti(n,p) Cross Sections using a DD Neutron Generator for Medical Isotope Studies
| Autor: | Andrew S. Voyles, E. F. Matthews, Paul R. Renne, J. D. Bauer, J. C. Batchelder, Daniel Rutte, L. A. Bernstein, M. S. Basunia, M.A. Unzueta, Tim A. Becker, K. van Bibber |
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| Rok vydání: | 2017 |
| Předmět: |
Nuclear and High Energy Physics
Isotope 010308 nuclear & particles physics Chemistry Nuclear data FOS: Physical sciences Inelastic scattering 01 natural sciences 3. Good health Semiconductor detector Cross section (geometry) Nuclear physics Neutron generator 13. Climate action 0103 physical sciences Neutron source Neutron Nuclear Experiment (nucl-ex) 010306 general physics Instrumentation Nuclear Experiment |
| DOI: | 10.48550/arxiv.1704.08761 |
| Popis: | 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. 12 pages, submitted to NIM-B |
| Databáze: | OpenAIRE |
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