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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Teresa Orellana Pérez, Holger Voelzke, Dietmar Wolff, Uwe Zencker (BAM)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 718-725
The current German waste management strategy consists of dry interim storage of spent fuel inside dual purpose casks at various sites and its subsequent direct final disposal in a deep geological repository. Interim facilities are licensed for up to 40 years of operation but this storing period will have to be extended until repository site selection and operation is concluded, potentially up to 100 years. In this context, research on long term mechanical behavior of fuel cladding and cask components during extended interim storage and transportation to a final repository are of outmost importance.
Barrier properties of the fuel cladding depend on its integrity which is affected over time by thermo-mechanical loads and by microstructure altering including potential embrittlement caused by re-oriented hydride precipitation. Experimental and numerical investigations have been performed by the international research community in order to predict the degree of cladding embrittlement against storage time. Results have shown that embrittlement of cladding materials is governed by the concentration, orientation and size of precipitated hydrides. Nevertheless, the existing variety of fuel materials and assemblies available on the market and the many parameters effecting hydride precipitation do not allow sufficient reliable safety predictions in the long term without further investigation.
Thus, knowledge on cladding integrity over storage time and during subsequent transportation is to be gained taking into consideration the relevant fuel and cladding material types as well as cladding temperatures along with peak values during cask drying and cooling rates during storage periods. Expected research results will increase the accuracy of cladding safety analysis. This paper summarizes the current German status regarding extended interim storage and how BAM is going to identify and address potential cladding integrity issues in the long term.