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Radium sources yield cancer-fighting Ac-225 in IAEA program
The International Atomic Energy Agency has reported that, to date, 14 countries have made 14 transfers of disused radium to be recycled for use in advanced cancer treatments under the agency’s Global Radium-226 Management Initiative. Through this initiative, which was launched in 2021, legacy radium-226 from decades-old medical and industrial sources is used to produce actinium-225 radiopharmaceuticals, which have shown effectiveness in the treatment of patients with breast and prostate cancer and certain other cancers.
Michael F. Roche, Leonard Leibowitz, Jack L. Settle, Carl E. Johnson, Richard C. Vogel, Robert L. Ritzman
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 96-116
Technical Paper | Material | doi.org/10.13182/NT91-A35536
Articles are hosted by Taylor and Francis Online.
The vaporization of strontium, barium, and lanthanum from mixtures of their oxides with urania, zir-conia, and concrete is determined with the objective of understanding the release of these refractory fission products during the core/concrete interaction phase of a degraded core accident. The vaporization of uranium and the total mass vaporized are also determined. Three different concretes having silica contents ranging from 7 to 69 wt% are used to reflect the known range of reactor basemat compositions. In the experiments, the mixtures are vaporized at 2150 or 2400 K into flowing H2 or He-6 H2 gas. The total mass of material that was vaporized is determined by weighing the condensates; the masses of individual elements are determined by chemical analyses of the condensates. The phases present in the heated mixtures are inferred from electron probe microanalyses and X-ray diffraction analyses. Equilibrium calculations are performed using SOLGASMIX and a thermodynamic data base containing 112 gaseous and 108 condensed species. The partial molar free energy of oxygen is calculated from the equilibrium oxygen pressure established in the high-temperature reaction zone between the gas and the sample. Using this experimental data, the release to be expected in the molten core/concrete interaction phase of a severe nuclear reactor accident is estimated. The estimated release of strontium, barium, lanthanum, and uranium is <1% with a basemat concrete of low silica content (7 wt%) and decreases to <0.01% with a basemat concrete of high silica content (69 wt%). The estimated total mass release is ∼0.5% with all three concrete types.