Publications by authors named "Mark Brugh"

Developing targeted α-therapies has the potential to transform how diseases are treated. In these interventions, targeting vectors are labelled with α-emitting radioisotopes that deliver destructive radiation discretely to diseased cells while simultaneously sparing the surrounding healthy tissue. Widespread implementation requires advances in non-invasive imaging technologies that rapidly assay therapeutics.

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Purpose: Thorium-226 (half-life 30.6 m) is a radionuclide of interest for use in targeted alpha therapy applications. Due to its short half-life, Th must be provided through a radionuclide generator system from its parent U (20.

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The alpha-emitter Ac (t = 9.92 d) is currently under development for targeted alpha-particle therapy of cancer, and accelerator production of Ac via proton irradiation of thorium targets requires robust separations of Ac from chemically similar fission product lanthanides. Additionally, the lanthanide elements represent critical components in modern technologies, and radiolanthanides such as Nd (t = 3.

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Increasing access to the short-lived α-emitting radionuclide astatine-211 (At) has the potential to advance targeted α-therapeutic treatment of disease and to solve challenges facing the medical community. For example, there are numerous technical needs associated with advancing the use of At in targeted α-therapy, e.g.

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Uranium-230 (t = 20.8 d) is an alpha-emitting radionuclide that has potential application in targeted alpha therapy (TAT) of cancer. Its parent isotope Pa (t = 17.

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Radionuclides find widespread use in medical technologies for treating and diagnosing disease. Among successful and emerging radiotherapeutics, Sb has unique potential in targeted therapeutic applications for low-energy electron-emitting isotopes. Unfortunately, developing Sb-based drugs has been slow in comparison to other radionuclides, primarily due to limited accessibility.

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Protactinium-230 ( t = 17.4 d) is the parent isotope of U ( t = 20.8 d), a radionuclide of interest for targeted alpha therapy (TAT).

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The separation of Th, Pa, and U is of high importance in many applications including nuclear power, nuclear waste, environmental and geochemistry, nuclear forensics and nuclear medicine. Diglycolamide (DGA)-based resins have shown the ability to separate many elements, however, these resins consist of non-covalent impregnation of the DGA molecules on the resin backbone resulting in co-elution of the extraction molecule during separation cycles, therefore limiting their long-term and repeated use. Covalently binding the DGA molecules onto silica is one way to overcome this issue.

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Ruthenium-103 is the parent isotope of 103mRh (t1/2 56.1 min), an isotope of interest for Auger electron therapy. During the proton irradiation of thorium targets, large amounts of 103Ru are generated through proton induced fission.

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Column chromatographic methods have been developed to separate no-carrier-added Ag from proton irradiated thorium targets and associated fission products as an ancillary process to an existing Ac separation design. Herein we report the separation of Ag both prior and subsequent to Ac recovery using CL resin, a solvent impregnated resin (SIR) that carries an organic solution of alkyl phosphine sulfides (RP = S) and alkyl phosphine oxides (RP = O). The recovery yield of Ag was 93 ± 9% with a radiochemical purity of 99.

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A new method has been developed for the isolation of Ra, in high yield and purity, from a proton irradiated Th matrix. Herein we report an all-aqueous process using multiple solid-supported adsorption steps including a citrate chelation method developed to remove >99.9% of the barium contaminants by activity from the final radium product.

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Scandium-44g (half-life 3.97h) shows promise for application in positron emission tomography (PET), due to favorable decay parameters. One of the sources of Sc is the Ti/Sc generator, which can conveniently provide this radioisotope on a daily basis at a diagnostic facility.

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Introduction: Rhenium-186g (t = 3.72 d) is a β emitting isotope suitable for theranostic applications. Current production methods rely on reactor production by way of the reaction Re(n,γ)Re, which results in low specific activities limiting its use for cancer therapy.

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