Analysis of the 148Gd and 154Dy Content in Proton-Irradiated Lead Targets

High precision half-life measurement of the extinct radio-lanthanide Dysprosium-154

Sixty years after the discovery of ¹⁵⁴Dy, the half-life of this pure alpha-emitter was re-measured. ¹⁵⁴Dy was radiochemically separated from proton-irradiated tantalum samples. Sector field- and multicollector-inductively coupled plasma mass spectrometry were used to determine the amount of ¹⁵⁴Dy retrieved. The disintegration rate of the radio-lanthanide was measured by means of α-spectrometry. The half-life value was determined as (1.40 ± 0.08)∙10⁶ y, with an uncertainty reduced by a factor of ~ 10 compared to the currently adopted value of (3.0 ± 1.5)∙10⁶ y. This precise half-life value is useful for the the correct testing and evaluation of p-process nucleosynthetic models using ¹⁵⁴Dy as a seed nucleus or as a reaction product, as well as for the safe disposal of irradiated target material from accelerator driven facilities. As a first application of the half-life value determined in this work, the excitation functions for the production of ¹⁵⁴Dy in proton-irradiated Ta, Pb, and W targets were re-evaluated, which are now in agreement with theoretical calculations.

Radiochemical Determination of Long-Lived Radionuclides in Proton-Irradiated Heavy Metal Targets: Part II Tungsten

In this study, proton-irradiated tungsten targets, up to 2.6 GeV, were investigated for the purpose of the experimental cross-section measurements. Radiochemical separation methods were applied to isolate the residual long-lived alpha-emitters ¹⁴⁸Gd, ¹⁵⁴Dy, and ¹⁴⁶Sm and the beta-emitters ¹²⁹I and ³⁶Cl from proton-irradiated tungsten targets. The molecular plating technique has been applied to prepare ¹⁴⁸Gd, ¹⁵⁴Dy, and ¹⁴⁶Sm samples for alpha-spectrometry. Production cross-sections of ¹²⁹I and ³⁶Cl were determined by means of accelerator mass spectrometry. The results are compared with theoretical predictions, obtained with the INCL++-ABLA07 codes, showing good agreement for ³⁶Cl and ¹⁴⁸Gd, while a factor of 4 difference was observed for ¹⁵⁴Dy, similar to the results obtained for tantalum targets.

Determination of the gamma and X-ray emission intensities of erbium-169

The gamma and X-ray emission intensities of ¹⁶⁹Er were determined using radionuclidically pure ¹⁶⁹Er. The activity of the ¹⁶⁹Er source was standardized by the triple-to-double-coincidence ratio technique. Three independent measurements were performed to measure the emission intensities using calibrated high-purity germanium spectrometers. The efficiencies were computed with the Monte Carlo method and validated using several experimental measurements. Final results present a large uncertainty reduction compared to previous evaluations. The emission intensities per decay of ¹⁶⁹Er are reported as 1.401(40).10^-5 for the 109.8 keV line and 1.513(19).10^-6 for the 118.2 keV line. The values obtained for the X-ray lines show large discrepancies with the reference values.

Production of Mass-Separated Erbium-169 Towards the First Preclinical in vitro Investigations

The β--particle-emitting erbium-169 is a potential radionuclide toward therapy of metastasized cancer diseases. It can be produced in nuclear research reactors, irradiating isotopically-enriched 168Er2O3. This path, however, is not suitable for receptor-targeted radionuclide therapy, where high specific molar activities are required. In this study, an electromagnetic isotope separation technique was applied after neutron irradiation to boost the specific activity by separating 169Er from 168Er targets. The separation efficiency increased up to 0.5% using resonant laser ionization. A subsequent chemical purification process was developed as well as activity standardization of the radionuclidically pure 169Er. The quality of the 169Er product permitted radiolabeling and pre-clinical studies. A preliminary in vitro experiment was accomplished, using a 169Er-PSMA-617, to show the potential of 169Er to reduce tumor cell viability.

Development of 148Gd analysis method using stable Gd

The analytical method of Gd determination was developed with the aim to analyse ¹⁴⁸Gd in environmental and bioassay samples. It involves the use of anion exchange resin, extraction chromatography, and cation exchange resin. Alkaline fusion and calcium oxalate co-precipitation are used for solid samples dissolution and liquid samples preconcentration, respectively. Total method recovery was tested with natural Gd (¹⁵⁷Gd) using ICP-QQQ-MS. A maximum total recovery of 75 % was obtained.

Radiochemical Determination of Long-Lived Radionuclides in Proton-Irradiated Heavy-Metal Targets: Part I-Tantalum

In this study, distillation, precipitation, and ion-exchange methods were chosen for the separation of the long-lived β-emitters ¹²⁹I, ³⁶Cl and the α-emitters ¹⁵⁴Dy, ¹⁴⁸Gd, ¹⁵⁰Gd, and ¹⁴⁶Sm from Ta targets irradiated with protons up to 2.6 GeV to determine their production cross sections. Measurements of ¹²⁹I/¹²⁷I and ³⁶Cl/³⁵Cl ratios were performed with accelerator mass spectrometry. After separation of the lanthanides, the molecular plating technique was applied to prepare thin samples to obtain highly resolved α-spectra. Autoradiography and focused ion beam/scanning electron microscopy techniques were used to characterize the lanthanide deposited layer. Experimental cross-section data are compared with theoretical predictions obtained with INCL++ and ABLA07 code, and a satisfactory agreement is observed.