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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Oklo signs MOU to partner with Korea Hydro & Nuclear Power
Oklo cofounder and CEO Jacob DeWitte and KHNP CEO Joo-ho Whang following the virtual signing of an MOU. (Source: Oklo)
Oklo announced last week that it hopes to expand development and global deployment of its advanced nuclear technology through a new partnership with Korea Hydro & Nuclear Power.
The memorandum of understanding includes plans for the companies to advance standard design development and global deployment of Oklo’s planned Aurora Powerhouse, a microreactor that would generate 15 MW and be scalable to 50 MWe. Oklo said each unit can operate for 10 years or longer before refueling.
Oklo and KHNP plan to cooperate on early-stage project development, including manufacturability assessments and planning of major equipment, supply chain development for balance-of-plant systems, and constructability assessments and planning.
Yunmin Yang, Naoto Sekimura, Hiroaki Abe
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 460-464
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A378
Articles are hosted by Taylor and Francis Online.
In this study, MD simulations of compression process were carried for copper lattices with an interstitial type Frank loops. Slipping of prismatic dislocations was not observed for loops whose size ranges from 0.5nm to 3.6nm. For loops with a size of 0.5nm, atoms in loops were squeezed into the neighboring layer to form crowdion bundles along <110> directions, and then swept away by further deformation. For loops larger than 2nm, the movements of atoms in faulted layer were not homogeneously in one direction during elastic deformation process, its extrinsic stacking was broken into two intrinsic ones exist on two successive planes. After yielding the slipping on these two successive planes accommodated the plastic deformation and broke up the loop. The results in this work proved that, for low stacking fault energy FCC metals such as copper and stainless steel, to describe their deformation mechanism after neutron or heavy ion irradiation, unfaulting and prismatic slipping mechanism cannot apply for interstitial Frank loops, and the behavior of these loops have dependence on their size and Schmid factor.