arXiv subjects

E. F. Matthews

Publications and source records attributed to E. F. Matthews.

5 recordsLinked to original sources

arXiv2026

Statistical and non-statistical $γ$-decay properties of $^{64}$Zn

We present a study on the $γ$-decay properties of $^{64}$Zn using the Oslo method on $^{64}$Zn($p,p^\prime γ$) data combined with $^{64}$Zn$(γ,n)$ cross-section measurements at the NewSUBARU facility. With the Oslo method, we have measured the $γ$-ray strength function ($γ$SF) and the nuclear level density (NLD) below the neutron threshold. We observe that the NLD trend in the quasi-continuum region of $^{64}$Zn is best characterized by a constant-temperature-like model. %with temperature parameter $T_{\rm CT}=1.21(5)$ MeV. Surprisingly, we find that $γ$-ray transitions from the quasi-continuum decaying directly to the $0^+$ ground state seem to be strongly hindered with a hindrance factor of $κ\approx 0.5$, which could be an indication of non-statistical effects in the ground-state decay due to, \textit{e.g.}, differences in nuclear shapes. For $γ$ energies above the neutron separation energy, the NewSUBARU ($γ, n$) data set probes a significant part of the giant dipole resonance. Furthermore, we find that the Oslo-method $γ$SF shows a rather smooth behavior, with a clear low-energy enhancement (LEE) for $E_γ < 4$ MeV.

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arXiv2026

Exploring the statistical properties of the neutron-deficient $^{109}$In isotope with the Oslo method

The nuclear level density (NLD) and the $γ$-ray strength function (GSF) of the neutron-deficient $^{109}$In isotope were extracted for the first time with data from the $^{106}$Cd$(α,pγ)^{109}$In reaction using a combination of the Oslo and the shape methods. Both quantities are consistent with those of neighboring Cd and Sn nuclei, but show substantial discrepancies with currently available model predictions. In contrast to earlier observations in the neighboring isotopic chains, $^{109}$In does not exhibit any significant enhancement of the dipole strength near the neutron separation energy. To interpret this feature, random-phase time-blocking approximation calculations have been performed for $^{109}$In and the neighboring $^{110,112}$Sn nuclei. The experimental data were also employed to estimate cross sections and rates of the radiative neutron- and proton-capture reactions, $^{108}$In($n,γ)$$^{109}$In and $^{108}$Cd($p,γ)$$^{109}$In, respectively, with the reaction code TALYS. Our ($p,γ)$ cross section is in excellent agreement with direct measurements over a wide range of proton energies, while the ($n,γ)$ cross section demonstrates notable deviations from predictions in the JINA REACLIB library. The new results on the statistical properties of $^{109}$In provide valuable constraints that may help address the problem of large model uncertainties compromising the accuracy of astrophysical $p$-process simulations.

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arXiv2025

Nuclear excitation functions for medical isotope production: targeted radionuclide therapy via natIr(d,x)193mPt

193mPt is an Auger emitting radionuclide which may have therapeutic potential, particularly when labeled to the chemotherapeutic drug cisplatin. One challenge to broader explorations of its clinical potential is the need for production routes with high specific activity. As part of a larger campaign to address gaps in reaction data for emerging medical radionuclides, this work seeks to characterize the natIr(d,x) reactions as a potential production pathway for 193mPt. A stacked target irradiation, consisting of natural iridium, iron, nickel, and copper foils, was performed using a 33 MeV deuteron beam at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. This measurement, along with previous experimental data, suggests an energy window between 11 to 18 MeV to maximize the production and radiopurity of 193mPt. This experiment has yielded cross sections for 43 channels of deuteron-induced reactions from threshold to 30 MeV, including the first experimental results of natIr(d,x)188m1+g,190m1+gIr (cumulative), natNi(d,x)56,57,58m,58gCo (independent), natCu(d,x)61Co (cumulative) and natFe(d,x)53Fe, 48V (cumulative). The results were compared with literature data, the TENDL-2023 database, and default theoretical calculations from the TALYS-2.04, CoH-3.6.0, EMPIRE-3.2.3, and ALICE-2020 reaction modeling codes. This work presents another example of the lack of predictive capabilities for this set of modern nuclear-reaction modeling codes, and highlights the unsatisfactory modeling of experimental cross sections. Experimental data are important to improve the codes in general, and new experimental results can be used to improve the models. Finally, this measurement has revealed the need for an updated evaluation of the natCu(d,x)63Zn deuteron monitor reaction.

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arXiv2020

FIER: Software for analytical modeling of delayed gamma-ray spectra

A new software package, the Fission Induced Electromagnetic Response (FIER) code, has been developed to analytically predict delayed $γ$-ray spectra following fission. FIER uses evaluated nuclear data and solutions to the Bateman equations to calculate the time-dependent populations of fission products and their decay daughters resulting from irradiation of a fissionable isotope. These populations are then used in the calculation of $γ$-ray emission rates to obtain the corresponding delayed $γ$-ray spectra. FIER output was compared to experimental data obtained by irradiation of a $^{235}$U sample in the Godiva critical assembly. This investigation illuminated discrepancies in the input nuclear data libraries, showcasing the usefulness of FIER as a tool to address nuclear data deficiencies through comparison with experimental data. FIER provides traceability between $γ$-ray emissions and their contributing nuclear species, decay chains, and parent fission fragments, yielding a new capability for the nuclear science community.

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arXiv2020

Neutron Spectroscopy for Pulsed Beams with Frame Overlap using a Double Time-of-Flight Technique

A new double time-of-flight (dTOF) neutron spectroscopy technique has been developed for pulsed broad spectrum sources with a duty cycle that results in frame overlap, where fast neutrons from a given pulse overtake slower neutrons from previous pulses. Using a tunable beam at the 88-Inch Cyclotron at Lawrence Berkeley National Laboratory, neutrons were produced via thick-target breakup of 16 MeV deuterons on a beryllium target in the cyclotron vault. The breakup spectral shape was deduced from a dTOF measurement using an array of EJ-309 organic liquid scintillators. Simulation of the neutron detection efficiency of the scintillator array was performed using both GEANT4 and MCNP6. The efficiency-corrected spectral shape was normalized using a foil activation technique to obtain the energy-dependent flux of the neutron beam at zero degrees with respect to the incoming deuteron beam. The dTOF neutron spectrum was compared to spectra obtained using HEPROW and GRAVEL pulse height spectrum unfolding techniques. While the unfolding and dTOF results exhibit some discrepancies in shape, the integrated flux values agree within two standard deviations. This method obviates neutron time-of-flight spectroscopy challenges posed by pulsed beams with frame overlap and opens new opportunities for pulsed white neutron source facilities.

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