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Andrew Voyles

Publications and source records attributed to Andrew Voyles.

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Nuclear Data Needs for Microcalorimetry and Non-destructive Assay

Cryogenic microcalorimeters are state-of-the-art radiation detectors using superconducting and quantum technologies. They can resolve complex X-ray and low-energy {\gamma}-ray spectra with ultra-high energy resolution of an order of 10 eV at 100 keV, enabling high-precision non-destructive assay (NDA) analysis of nuclear materials containing uranium, plutonium and other actinides. With significant technical advancements in microcalorimetry technology, microcalorimeters are now deployable to end-users such as the International Atomic Energy Agency (IAEA) for improved NDA. However, the accuracy of microcalorimetry analysis can be limited by nuclear data. There are several cases that the current nuclear data obtained by conventional radiation detector technologies is not sufficient to support microcalorimetry analysis. To address the growing need for improved nuclear data in microcalorimetry, the U.S. Department of Energy Office of International Nuclear Safeguards hosted a workshop on Microcalorimetry and Nuclear Data (MiND) in June 2023. Microcalorimetry experts and users, and nuclear structure evaluators and managers, and program sponsors attended the workshop with the main objective of identifying a roadmap for priority nuclear data, stakeholders, partnerships, and opportunities. This paper summarizes the outcome of the MiND workshop, including the priority list of nuclear data for microcalorimetry and a multi-laboratory measurement campaign to improve such nuclear data.

physics.ins-det

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

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.

nucl-ex