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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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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.
I. Di Piazza, D. Martelli, C. Carrelli, T. Rovai, V. Raschioni, M. Ramacciotti, A. Spezzaneve, D. Ferretti, G. Mongiardini
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 681-691
Research Article | doi.org/10.1080/00295450.2023.2203285
Articles are hosted by Taylor and Francis Online.
The present paper describes the experimental setup for flow-induced vibration in a fuel pin bundle test section with flowing lead. The test section is a 37-pin mock-up representative of the GEN-IV ALFRED fuel assembly and is manufactured to investigate the turbulence-induced vibrations in the pins. The pins are instrumented with longitudinal strain gauges (SGs), and with three SGs per monitoring point, the displacement signal can be recovered in terms of amplitude and frequencies. To achieve this goal, a complex algorithm is implemented in the data acquisition control system of the test section. The test section will be installed in the Heavy Liquid metal Experimental loop for Nuclear Applications (HELENA) facility at the ENEA Brasimone R.C., in which a mechanical pump for lead circulation is present. The test matrix is proposed with the mass flow rate varying from 10 to 50 kg/s and a constant temperature of 450°C for all the tests. Briefly, the experimental procedure is presented to carry out the experimental campaign.