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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Oklo to collaborate with Atomic Alchemy on isotope production
Fast reactor developer Oklo, which recently went public on the New York Stock Exchange, announced on May 13 that it has signed a memorandum of understanding with Atomic Alchemy to cooperate on the production of radioisotopes for medical, energy, industry, and science applications.
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.