Abstract: The present invention provides a method for large scale production of cesium-131 (Cs-131) with low cesium-132 (Cs-132) content, where the Cs-131 is produced via barium-131 (Ba-131) decay. Uses of the Cs-131 produced by the method include cancer research and treatment, such as for use in brachytherapy. Cesium-131 is particularly useful in the treatment of faster growing tumors.

Abstract: The present invention provides a method for improving the recovery of cesium-131 (Cs-131) from barium (Ba) carbonate. Uses of the Cs-131 purified by the method include cancer research and treatment, such as for the use in brachytherapy. Cesium-131 is particularly useful in the treatment of faster growing tumors.

Abstract: The present invention provides a method for improving the recovery of cesium-131 (Cs-131) from barium (Ba) carbonate. Uses of the Cs-131 purified by the method include cancer research and treatment, such as for the use in brachytherapy. Cesium-131 is particularly useful in the treatment of faster growing tumors.

Abstract: Backfilled, self-assembled monolayers and methods of making the same are disclosed. The self-assembled monolayer comprises at least one functional organosilane species and a substantially random dispersion of at least one backfilling organosilane species among the functional organosilane species, wherein the functional and backfilling organosilane species have been sequentially deposited on a substrate. The method comprises depositing sequentially a first organosilane species followed by a backfilling organosilane species, and employing a relaxation agent before or during deposition of the backfilling organosilane species, wherein the first and backfilling organosilane species are substantially randomly dispersed on a substrate.

Abstract: A method and apparatus for isolating and purifying a 213Bi radioactive isotope from an 225Ac source using a primary column and a primary sorbent which preferentially retains 225Ac over 213Bi when exposed to a compatible solvent in combination with a secondary column having a secondary sorbent which retains 213Bi when exposed to a mixture of the compatible solvent and 213Bi. A “compatible solvent” is a solvent which will preferentially remove 213Bi radioactive isotopes from a primary sorbent without removing 225Ac radioactive isotopes, and then allow 213Bi radioactive isotopes removed from the primary sorbent to be retained on a secondary sorbent, without having to dilute or otherwise chemically or physically modify the compatible solvent in between exposure to the primary and secondary sorbents.