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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
Yang Hong Jung, Seung Je Baik, Young Gwan Jin
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 94-102
Technical Paper | doi.org/10.1080/00295450.2020.1738795
Articles are hosted by Taylor and Francis Online.
A radioactive corrosion product, Chalk River unidentified deposit (crud) was sampled and analyzed using an electron probe micro-analyzer with zinc-injected spent nuclear fuel rods (HU Unit 1, actual burnup 49 655 MWd/tonne U). Hot-cell facilities, a space for handling highly radioactive materials, were used as a way to collect crud deposited in the fuel rod cladding tube at a specific location of the spent fuel rod. A soft collection method for collecting crud using rubbings or adhesive tape was used to collect a sample, and a sample was collected with hard collection using a steel knife from the cladding tube of the fuel rod. The spent fuel rods were used for two cycles burned after zinc was injected into the primary coolant, which is known to inhibit the generation of crud. To compare the analysis results of the soft and hard collection methods for sampling crud, the results of the crud collected using an ultrasonic wave system were analyzed. The crud used in this study used burned fuel rods for two cycles after zinc ions were injected into the primary coolant. Based on the results, the Ni/Fe ratio can be estimated to be about 1.18. The Ni/Fe ratio value of 1.18 derived from this study is not much different from the Ni/Fe ratio values derived from nuclear power plants operating around the world.