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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
Yu. Igitkhanov, R. Fetzer, B. Bazylev, L. Boccaccini
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 516-520
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-943
Articles are hosted by Taylor and Francis Online.
Thermo-hydraulic analyses of the tungsten mono-block divertor module with a water cooling tube made from a diamond/copper composite (DCC) as a laminate and a martensitic steel EUROFER against the power loadings expecting in DEMO operation is presented. Thermal analysis is carried out by using the code MEMOS, which simulates W armor damage under the repetitive edge localized modes (ELM) heat impact. Heat transfer to the water coolant is studied for various coolant conditions which allow one to keep the material temperatures within the allowable design limits under neutron irradiation. The thermal performance is analyzed for the DEMO I and DEMO II reactor conditions for un-mitigated and mitigated ELMs. The importance of W vapor shielding effect is discussed.