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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
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.