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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.
N. Hashimoto, R. L. Klueh, M. Ando, H. Tanigawa, T. Sawai, K. Shiba
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 490-494
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST44-490
Articles are hosted by Taylor and Francis Online.
In order to determine the contributions of different microstructural features to strength and to deformation mode, microstructure of deformed flat tensile specimens of irradiated reduced activation F82H (IEA heat) base metal (BM) and its tungsten inert-gas (TIG) weldments (weld metal and weld joint) were investigated by transmission electron microscopy (TEM), following fracture surface examination by scanning electron microscopy (SEM). After irradiation, the fracture surfaces of F82H BM and TIG weldment showed a martensitic mixed quasi-cleavage and ductile-dimple fracture. The microstructure of the deformed region of irradiated F82H BM contained dislocation channels. This suggests that dislocation channeling could be the dominant deformation mechanism in this steel, resulting in the loss of strain-hardening capacity. While, the necked region of the irradiated F82H TIG, where showed less hardening than F82H BM, showed deformation bands only. From these results, it is suggested that the pre-irradiation microstructure, especially the dislocation density, could affect the post-irradiation deformation mode.