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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
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.
Afaque Shams, Dante De Santis (NRG), Adam Padee, Tobiasz Jarosiewicz, Piotr Wasiuk, Tomasz Kwiatkowski, S?awomir Potempski (National Centre for Nuclear Research)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 625-635
This paper presents technical aspects of large-scale direct numerical simulation (DNS) using high performance computing (HPC) cluster. It is divided in two parts. The first part contains a detailed description of HPC infrastructure used for the task, located in ?wierk Computing Centre (CI?), Poland. The description includes hardware configuration, software used for on-demand deployment of dedicated subclusters, and finally queuing and storage systems. The second part presents the large-scale simulations performed using this HPC cluster. In this regard, a highly scalable CFD code NEK5000 has been used to perform the DNS of two important thermal-hydraulic problems within the nuclear industry, i.e. pressurized thermal shock and inter-channel mixing in a bare rod bundle configuration.
