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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
T. M. Krishnamoorthy, S. N. Joshi, G. R. Doshi, R. N. Nair
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 351-357
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34896
Articles are hosted by Taylor and Francis Online.
Leach characteristics of some typical nuclides such as cesium, strontium, cobalt, I−, and CO3−2 from ordinary portland cement waste forms have been studied using the ISO test method and radiotracers of the respective nuclides, i.e., 134Cs, 85Sr, 60Co, 131I, and 14C. The leach studies suggest a rapid release of radioactivity in the beginning (fast component) followed by slow release for long periods of time (slow component). A mathematical model has been simulated to describe the leaching kinetics of these nuclides from the cement matrix. The effective diffusion coefficient Deff is computed from the two componental diffusion coefficients, and the retardation factor (α) for a nuclide is evaluated from a knowledge of the radioactivity distribution in the aqueous and solid phase at equilibrium. The product αDeff for all the nuclides studied has been found to be approximately constant and is equal to the intrinsic diffusion coefficient in the cement matrix. The net fractional release of different radionuclides from cement waste form showed a decreasing pattern, i.e., 134Cs > 131I > 85Sr > 14Cr > 60Co indicating the largest diffusion coefficient for cesium as 10−2 cm2/day and the least for 14C as 3 × 10−8 cm2/day.