Measurement of the 64Zn,47Ti(n,p) cross sections using a DD neutron generator for medical isotope studies

Voyles, Andrew S.; Basunia, M. S.; Batchelder, J.C.; Bauer, J. D.; Becker, T.; Bernstein, L. A.; Matthews, E. F.; Renne, Paul R.; Rutte, Daniel; Unzueta, Mauricio Ayllon; Bibber, Karl A. van

doi:10.1016/j.nimb.2017.08.021

“…As seen with ALICE for 61 Cu/ 64 Cu, the alternating underestimation/overestimation across channels for a single code points to competition between neighboring reaction channels as a common issue in this mass region. nat Cu(p,x) also yielded measurements of a number of additional medical radionuclides, including the non-standard positron emitters 57 Ni [7,[80][81][82], 61 Cu [83,84], and 64 Cu [85][86][87][88][89][90][91][92]. However, production of these radionuclides offers no major advantages over established pathways, with the lower yield and radioisotopic purity failing to justify the convenience of natural targets via nat Cu(p,x).…”

Section: 109625mentioning

confidence: 99%

Proton-induced reactions on Fe, Cu, and Ti from threshold to 55 MeV

Voyles

¹

,

Lewis

²

,

Morrell

³

et al. 2021

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Theoretical models often differ significantly from measured data in their predictions of the magnitude of nuclear reactions that produce radionuclides for medical, research, and national security applications. In this paper, we compare a priori predictions from several state-of-the-art reaction modeling packages (CoH, EMPIRE, TALYS, and ALICE) to cross sections measured using the stacked-target activation method. The experiment was performed using the Lawrence Berkeley National Laboratory 88-Inch Cyclotron with beams of 25 and 55 MeV protons on a stack of iron, copper, and titanium foils. Thirty-four excitation functions were measured from 4–55 MeV, including the first measurement of the independent cross sections for $$^{\mathrm{nat}}\hbox {Fe}$$ nat Fe (p,x)$$^{49,51}\hbox {Cr}$$ 49 , 51 Cr , $$^{51,{\mathrm{52m}},{\mathrm{52g}},56}\hbox {Mn}$$ 51 , 52 m , 52 g , 56 Mn , and $$^{{\mathrm{58m,58g}}}\hbox {Co}$$ 58 m , 58 g Co . All of the models, using default input parameters to assess their predictive capabilities, failed to reproduce the isomer-to-ground state ratio for reaction channels at compound and pre-compound energies, suggesting issues in modeling the deposition or distribution of angular momentum in these residual nuclei.

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“…In addition to the nat Fe(p,x) 51,52 Mn measurements, this experiment has also yielded measurements of a number of additional emerging radionuclides with medical applications. These include the non-standard positron emitters 44 Sc [48][49][50] 55 Co [51][52][53] 61 Ni [7,[54][55][56], 61 Cu [57,58] 64 Cu [59][60][61][62][63][64][65][66], and the β − -therapeutic agent 47 Sc [67,68]. Production of these radionuclides offers no major advantages over established pathways, with the generally lower yields and radioisotopic purities failing to justify the convenience of natural targets via nat Fe(p,x), nat Cu(p,x), and nat Ti(p,x).…”

Section: Code Versionmentioning

confidence: 99%

Proton-induced reactions on Fe, Cu, & Ti from threshold to 55 MeV

Voyles,

Lewis,

Morrell

et al. 2019

Preprint

0

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Theoretical models often differ significantly from measured data in their predictions of the magnitude of nuclear reactions that produce radionuclides for medical, research, and national security applications. In this paper, we compare a priori predictions from several state-of-the-art reaction modeling packages (CoH, EMPIRE, TALYS, and ALICE) to cross sections measured using the stacked-target activation method. The experiment was performed using the LBNL 88-Inch Cyclotron with beams of 25 and 55 MeV protons on a stack of iron, copper, and titanium foils. 34 excitation functions were measured for 4 < Ep < 55 MeV, including the first measurement of the independent cross sections for nat Fe(p,x) 49,51 Cr, 51,52m,52g,56 Mn, and 58m,58g Co. All of the models failed to reproduce the isomer-to-ground state ratio for reaction channels at compound and pre-compound energies, suggesting issues in modeling the deposition or distribution of angular momentum in these residual nuclei.

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“…Moreover, we also present a semi-analytical approach based on the interaction processes within the target which can be used in order to gain greater insight and guide future neutron source developments. Additionally, it is important to model the neutron energy distribution in the lab frame for a variety of experiments including cross-section measurements [5].…”

Section: Modeling Of the Neutron Yield Flux And Energy Distributionmentioning

confidence: 99%

“…As a result, the types of neutron sources considered in the model were point-like, disk (D = 5 mm), and Gaussian shaped (FWHM = 7.2 mm ), with the latter taken from a best-fit model to ion beam optics simulations data. The results shown in this section apply only to a single-hole plasma electrode plate of 0.262 cm in diameter, which was used for several experiments including the one detailed in [5]. The code developed allows for different input parameters to be modified according to the experiment being performed.…”

Section: Neutron Flux and Energy Distributionmentioning

confidence: 99%

“…Since its commissioning, the HFNG has been proven useful for a variety of additional applications including Prompt Gamma Neutron Activation Analysis (PGNAA) for on-site gamma detector calibration, cross-section measurements for emerging medical isotopes [5], the study of delayed gamma rays from fission of 238 U, single event upset (SEU) of CPUs to develop radiation hardened electronics, the study of NaI detector response in neutron fields, and most recently, cross-section measurements of 35 Cl(n,p) 35 S and 35 Cl(n,α) 32 P, which are of significant interest for the design of molten salt reactors.…”

Section: Introductionmentioning

confidence: 99%

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Design, construction, and characterization of a compact DD neutron generator designed for 40Ar/39Ar geochronology

Ayllon,

Adams,

Bauer

et al. 2018

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0

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A next-generation, high-flux DD neutron generator has been designed, commissioned, and characterized, and is now operational in a new facility at the University of California Berkeley. The generator, originally designed for 40 Ar/ 39 Ar dating of geological materials, has since served numerous additional applications, including medical isotope production studies, with others planned for the near future. In this work, we present an overview of the High Flux Neutron Generator (HFNG) which includes a variety of simulations, analytical models, and experimental validation of results. Extensive analysis was performed in order to characterize the neutron yield, flux, and energy distribution at specific locations where samples may be loaded for irradiation. A notable design feature of the HFNG is the possibility for sample irradiation internal to the cathode, just 8 mm away from the neutron production site, thus maximizing the neutron flux (n/cm 2 /s). The generator's maximum neutron flux at this irradiation position is 2.58 ×10 7 n/cm 2 /s ± 5% (approximately 3×10 8 n/s total yield) as measured via activation of small natural indium foils. However, future development is aimed at achieving an order of magnitude increase in flux. Additionally, the deuterium ion beam optics were optimized by simulations for various extraction configurations in order to achieve a uniform neutron flux distribution and an acceptable heat load. Finally, experiments were performed in order to benchmark the modeling and characterization of the HFNG.

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Measurement of the 64Zn,47Ti(n,p) cross sections using a DD neutron generator for medical isotope studies

Cited by 15 publications

References 38 publications

Proton-induced reactions on Fe, Cu, and Ti from threshold to 55 MeV

Proton-induced reactions on Fe, Cu, and Ti from threshold to 55 MeV

Proton-induced reactions on Fe, Cu, & Ti from threshold to 55 MeV

Design, construction, and characterization of a compact DD neutron generator designed for 40Ar/39Ar geochronology

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