Engineering topics

Fassbender, Michael E.

Publications and source records attributed to Fassbender, Michael E..

6 records

DOE OSTI2024

An electrochemical generator for the continual supply of 213 Bi from 225 Ac for use in targeted alpha therapy applications

Bismuth-213 is a radionuclide of interest for targeted alpha therapy and is supplied via a radiochemical generator system through the decay of 225 Ac. Radionuclide generators employ longer lived “parent” radionuclides to routinely supply shorter-lived “daughter” radionuclides. The traditional 225 Ac/ 213 Bi radiochemical generator relies on an organic cation exchange resin where 225 Ac binds to the resin and 213 Bi is routinely eluted. These resins degrade when they absorb large doses of ionizing radiation (>1 × 10 6 Gy/mg), which has been observed when the loading activity of 225 Ac exceeds 2.59*10 9 Bq (70 mCi). Herein we report the development of an electrochemical generator for the supply of 213Bi that has the potential to overcome this limitation. Bismuth-213 spontaneously electrodeposits onto nickel foils in 0.1 M hydrochloric acid at 70 °C. Using this method, we were able to plate an average of 73 ± 4 % of the 213 Bi in solution and obtain a final 213 Bi recovery of 65 ± 8 % in 0.1 M citrate pH 4.5 via reverse electrolysis using titanium as the cathode. The recovered 213Bi had an average radiochemical purity of >99.8 % and was successfully used to radiolabel DOTATATE with an average radiochemical yield of 85.1 % (not optimized).

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

DOE OSTI2023

Production of zirconium-88 via proton irradiation of metallic yttrium and preparation of target for neutron transmission measurements at DICER

Abstract A process for the production of tens to hundreds of GBq amounts of zirconium-88 ( 88 Zr) using proton beams on yttrium was developed. For this purpose, yttrium metal targets (≈20 g) were irradiated in a ~16 to 34 MeV proton beam at a beam current of 100–200 µA at the Los Alamos Isotope Production Facility (IPF). The 88 Zr radionuclide was produced and separated from the yttrium targets using hydroxamate resin with an elution yield of 94(5)% (1σ). Liquid DCl solution in D 2 O was selected as a suitable 88 Zr sample matrix due to the high neutron transmission of deuterium compared to hydrogen and an even distribution of 88 Zr in the sample matrix. The separated 88 Zr was dissolved in DCl and 8 µL of the obtained solution was transferred to a tungsten sample can with a 1.2 mm diameter hole using a syringe and automated filling station inside a hot cell. Neutron transmission of the obtained 88 Zr sample was measured at the Device for Indirect Capture Experiments on Radionuclides (DICER).

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2021

Extractants and extractant compositions for radioisotope and metal recovery

Disclosed herein are embodiments of an extractant that can be used for chromatographic isolation of radioisotopes and/or metal species. The extractant can be combined with a support medium to provide an extractant composition that selectively and efficiently binds particular radioisotopes and/or metal species. Also disclosed herein are embodiments of a method for using the disclosed extractant embodiments, as well as embodiments of a method for making the extractant and extractant composition.

Stein, Benjamin W.↗

DOE OSTI2020

A reverse 230 U/ 226 Th radionuclide generator for targeted alpha therapy applications

Thorium-226 (half-life 30.6 m) is a radionuclide of interest for use in targeted alpha therapy applications. Additionally, due to its short half-life, 226 Th must be provided through a radionuclide generator system from its parent 230 U (20.8 d). Furthermore, as the half-life of 226 Th is very short, it should be provided in a form that is directly amenable to use in biomedical applications.

226-Th↗

DOE OSTI2020

Thorium chelators for targeted alpha therapy: Rapid chelation of thorium-226

We report one of the main challenges in targeted alpha therapy is assuring delivery of the α-particle dose to the targeted cells. Thus, it is critical to identify ligands for α-emitting radiometals that will form complexes that are very stable, both in vitro and in vivo. In this investigation, thorium-227 (t 1/2 = 18.70 days) chelation of ligands containing hydroxypyridinonate (HOPO) or picolinic acid (pa) moieties and the stability of the resultant complexes were studied. Chelation reactions were followed by reversed-phased HPLC and gamma spectroscopy. Studies revealed that high 227 Th chelation yields could be obtained within 2.5 h or less with ligands containing four Me-3,2-HOPO moieties, 1 (83%) and 2 (65%), and also with ligands containing pa moieties, H 4 octapa 3 (65%) and H 4 py4pa 6 (87%). No reaction occurred with H 4 neunpa-p-Bn-NO 2 4, and the chelation reaction with another pa ligand H 4 pypa 5 gave inconsistent yields with a very broad radio-HPLC peak. The ligands spermine-(Me-3,2-HOPO) 4 1, H 4 octapa 3, and H 4 py4pa 6 had high stability (i.e., 87% of 227 Th still bound to the ligand) in phosphate-buffered saline at room temperature over a 6-day period. Preliminary studies with ligand 6 demonstrated efficient chelation of thorium-226 (t 1/2 = 30.57 min) when heated to 80°C for 5 min.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

DOE OSTI2020

Method for producing thorium-226

Disclosed herein are embodiments of a method for producing thorium-226. The method comprises separating thorium-226 from uranium-230 to produce a solution of thorium-226 in a solvent, such as a chelating buffer, suitable for direct labeling by a chelate. The thorium-226 may be separated from the uranium-230 using extraction chromatography. The extraction may be repeated multiple times as additional thorium-226 is produced by uranium-230 decay.

07 ISOTOPE AND RADIATION SOURCES↗