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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Mária Chromčíková, Jana Vokelová, Jaroslava Michálková, Marek Liška, Jan Macháček, Ondrej Gedeon, Vojtech Soltész
Nuclear Technology | Volume 193 | Number 2 | February 2016 | Pages 297-305
Technical Paper | doi.org/10.13182/NT15-22
Articles are hosted by Taylor and Francis Online.
The chemical durability of gamma-irradiated glass fibrous insulation commonly used in the reactor containment of nuclear power plants was tested by static leaching tests at 90°C. Distilled water and borate coolant solution were used as corrosive media. Two radiation doses, 2 and 4 MGy, were applied, the higher one roughly corresponding to 30 years of irradiation in reactor containment. The glass insulation was irradiated at low (70°C) and increased (450°C) temperatures. The results of the static leaching tests were compared with those obtained for nonirradiated native glass fibers. In distilled water, higher normalized leached amounts of calcium were found for low-temperature-irradiated glass fibers and in the initial stage of leaching of high-temperature-irradiated glass fibers; the lower normalized leached amounts were found for boron for glasses irradiated at both temperatures. In the borate coolant solution, higher normalized leached amounts of calcium and lower leached amounts of aluminum were observed for glasses irradiated at both temperatures. In all cases, the results were comparable for both applied radiation doses. Moreover, extraordinary brittleness of the glass fibers irradiated at high temperature was observed. This principally new finding needs further experimental and theoretical investigation.