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https://www.selleckchem.com/products/mitoquinone-mesylate.html The half-life of 225Ac was determined from long-term measurements using an ionization chamber (IC) and a TDCR system. The combined result was found to be 9.9179(30) d, which is in agreement with the outcome from Pommé et al. (2012). For evaluating the counting efficiency of a portal monitor, we use a137Cs radiation point source (1 μCi) to subsequently establish it effective measurable area. Through simulation, we estimate the appropriate distance from potentially contaminated individuals in the scanning queue to the monitoring individual. When this distance is over 10 m, the counting efficiency was below 0.01%. We find that the triage can be applied to roughly 180 individuals per hour during mass casualties. Gallium-68 (68Ga) has attracted increasing interest in recent years due to the expanding clinical applications of 68Ga-based radiopharmaceuticals (Rahbar et al., 2017). 68Ga is mainly produced via 68Ge/68Ga generators that are limited in yield by the 68Ge activity (typically up to 1.85 GBq at calibration time). With the increased-demand of 68Ga in nuclear medicine for positron emission tomography (PET) imaging, there is a need for more efficient and robust production methods to obtain larger amounts of [68Ga]GaCl3 with high radionuclidic and radiochemical purity and apparent molar activity (AMA) for facilitating the distribution of 68Ga-based radiopharmaceuticals. The objectives of this study were to develop a fast and efficient process for the preparation of 68Zn-based solid targets and to optimize the critical parameters for the automated radiosynthesis of [68Ga]GaCl3 for large-scale routine production. Monte Carlo simulations (MCNP) were carried out to model suitable 252Cf-based gamma transmission and neutron attenuation geometries to evaluate the gamma-ray shielding features and neutron attenuation capabilities for Al2O3, MgF2, Fluental and AlF3, as fast neutron moderators of potential interest i

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