Preparation of a As source sample for application in an offline ion source.

For the generation of beams with the offline ion source at the Facility for Rare Isotope Beams (FRIB), suitable source samples are required. Arsenic-73 is a frequently requested user beam due to its significance in nuclear structure studies and astrophysics. In this work, we outline the process of preparing a As source sample, containing (5.

Production and separation of Be for use in an ion source.

Beryllium-7 (Be) was created by proton irradiation of natural (B) and enriched (B) boron targets. The targets were dissolved in nitric acid, and the Be was separated from the bulk boron target material by cation-exchange chromatography. An average recovery of (99.

Preparation of stable and long-lived source samples for the stand-alone beam program at the Facility for Rare Isotope Beams.

At the Facility for Rare Isotope Beams (FRIB), an oven-ion source combination was used to create rare isotope beams in support of the stand-alone user beam program of the ReAccelerator (ReA) facility. This ion source, called Batch-Mode Ion Source (BMIS), was loaded with enriched stable nuclides (Si, Cr, and Fe) and long-lived radionuclides (Al, Si). The introduced samples, herein designated as source samples, were thermally volatilized in the BMIS oven, and then ionization was used to generate the required beams.

Proof-of-concept studies of novel protocols for producing highly pure V from a Cr/V generator.

The quest to improve the quality of nuclear data, such as half-lives, transition yields, and reaction cross-sections, is a shared endeavor among various areas of nuclear science. V is a vanadium isotope for which experimental data on neutron reaction cross-sections is needed. However, traditional isotope production techniques cannot produce V with high enough isotopic purity for some of these measurements.

Harvesting Zr from heavy-ion beam irradiated tungsten at the National Superconducting Cyclotron Laboratory.

Tungsten is a commonly used material at many heavy-ion beam facilities, and it often becomes activated due to interactions with a beam. Many of the activation products are useful in basic and applied sciences if they can be recovered efficiently. In order to develop the radiochemistry for harvesting group (IV) elements from irradiated tungsten, a heavy-ion beam containing Zr was embedded into a stack of tungsten foils at the National Superconducting Cyclotron Laboratory and a separation methodology was devised to recover the Zr.

Solid-phase isotope harvesting of Zr from a radioactive ion beam facility.

During routine operation of the Facility for Rare Isotope Beams (FRIB), radionuclides will accumulate in both the aqueous beam dump and along the beamline in the process of beam purification. These byproduct radionuclides, many of which are far from stability, can be collected and purified for use in other scientific applications in a process called isotope harvesting. In this work, the viability of Zr harvesting from solid components was investigated at the National Superconducting Cyclotron Laboratory.

A Model for Radiolysis in a Flowing-Water Target during High-Intensity Proton Irradiation.

At the Facility for Rare Isotope Beams (FRIB), interactions between heavy-ion beams and beam-dump water will create a wide variety of radionuclides which can be accessed by a technique known as "isotope harvesting". However, irradiation of water is always accompanied by the creation of numerous radical, ionic, and molecular radiolysis products. Some of the radiolysis products have sufficiently long lifetimes to accumulate in the irradiated water and affect the harvesting chemistry.

Harvesting krypton isotopes from the off-gas of an irradiated water target to generate Br and Br.

A flowing-water target was irradiated with a 150 MeV/nucleon beam of Kr at the National Superconducting Cyclotron Laboratory to produce Kr and Kr. Real-time gamma-imaging measurements revealed the mass transport of the krypton radioisotopes through the target-water processing, or "isotope harvesting", system. The production rates were determined to be 2.

Therapeutic Potential of Sc in Comparison to Lu and Y: Preclinical Investigations.

Targeted radionuclide therapy with Lu- and Y-labeled radioconjugates is a clinically-established treatment modality for metastasized cancer. Sc is a therapeutic radionuclide that decays with a half-life of 3.35 days and emits medium-energy β-particles.

Scandium and terbium radionuclides for radiotheranostics: current state of development towards clinical application.

Currently, different radiometals are in use for imaging and therapy in nuclear medicine: Ga and In are examples of nuclides for positron emission tomography (PET) and single photon emission computed tomography (SPECT), respectively, while Lu and Ac are used for β- and α-radionuclide therapy. The application of diagnostic and therapeutic radionuclides of the same element (radioisotopes) would utilize chemically-identical radiopharmaceuticals for imaging and subsequent treatment, thereby enabling the radiotheranostic concept. There are two elements which are of particular interest in this regard: Scandium and Terbium.

Sc for labeling of DOTA- and NODAGA-functionalized peptides: preclinical in vitro and in vivo investigations.

Background: Recently, Sc (T = 3.97 h, Eβ = 632 keV, I = 94.3 %) has emerged as an attractive radiometal candidate for PET imaging using DOTA-functionalized biomolecules.

Production and separation of Sc for radiopharmaceutical purposes.

Background: The favorable decay properties of Sc and Sc for PET make them promising candidates for future applications in nuclear medicine. An advantage Sc (T = 3.89 h, Eβ = 476 keV [88%]) exhibits over Sc, however, is the absence of co-emitted high energy γ-rays.

Sc as useful β-emitter for the radiotheragnostic paradigm: a comparative study of feasible production routes.

Background: Radiotheragnostics makes use of the same molecular targeting vectors, labeled either with a diagnostic or therapeutic radionuclide, ideally of the same chemical element. The matched pair of scandium radionuclides, Sc and Sc, satisfies the desired physical aspects for PET imaging and radionuclide therapy, respectively. While the production and application of Sc was extensively studied, Sc is still in its infancy.

Cyclotron production of (44)Sc: From bench to bedside.

Introduction: (44)Sc, a PET radionuclide, has promising decay characteristics (T1/2 = 3.97 h, Eβ(+)av = 632 keV) for nuclear imaging and is an attractive alternative to the short-lived (68)Ga (T1/2 = 68 min, Eβ(+)av = 830 keV). The aim of this study was the optimization of the (44)Sc production process at an accelerator, allowing its use for preclinical and clinical PET imaging.