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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Stephanie H. Bruffey, Robert T. Jubin
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 159-169
Technical Paper | doi.org/10.1080/00295450.2017.1369802
Articles are hosted by Taylor and Francis Online.
In 2010, the Idaho National Laboratory was in the process of removing legacy materials from one of their hot cells. As part of this clean-out effort, five metal capsules and some loose zeolite material were identified as test specimens produced in the late 1970s as part of research and development (R&D) conducted under the Airborne Waste Management Program. This specific R&D effort examined the encapsulation of 85Kr within a collapsed zeolite structure for use as a potential waste form for long-term storage. These reclaimed capsules and loose material presented a unique opportunity to study a potential 85Kr waste form after three half-lives have elapsed. Of the five capsules, the walls of two had been cut or breached during previous experiments. The aim of this study was to produce mounted samples from the two breached samples that could be handled with minimal shielding, assess the physical condition and chemical composition of the capsule walls for each breached sample, and determine if any loss of capsule wall integrity was directly attributable to rubidium, the decay product of 85Kr. The sectioning and mounting of the breached capsules was successfully completed. The capsule wall of these 85Kr legacy waste form capsules was examined by optical microscopy and by scanning electron microscopy and energy-dispersive spectroscopy. Substantial corrosion was observed throughout each capsule wall. The bulk of the capsule wall was identified as carbon steel, while the weld material used in capsule manufacture and/or sealing was identified as stainless steel. A notable observation was that the material used for Kr encapsulation was found adhered to the walls of each capsule and had a chemical composition consistent with zeolite minerals. The results of studies on the retention of Kr by the encapsulation material will be discussed in a subsequent paper. Three legacy capsules remain in storage at Oak Ridge National Laboratory and may not have been breached. These represent an exciting opportunity for continued 85Kr waste form studies and will provide more indication as to whether the corrosion observed in Capsules 2 and 5 is attributable to the breach of the capsule, to Rb-induced corrosion, or to another cause.