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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.
K. Masaki, J. Yagyu, T. Arai, A. Kaminaga, K. Kodama, N. Miya, T. Ando, H. Hiratsuka, M. Saidoh
Fusion Science and Technology | Volume 42 | Number 2 | September-November 2002 | Pages 386-395
Technical Paper | doi.org/10.13182/FST02-A235
Articles are hosted by Taylor and Francis Online.
JT-60U has a variety of wall-conditioning methods such as baking of the vacuum vessel, helium Taylor discharge cleaning, helium glow discharge cleaning, tokamak discharge cleaning, and boronization. Using these wall-conditioning methods, the high-power operation of JT-60U has been successfully carried out with the carbon-based first wall. The material behavior of the carbon-based first wall has been investigated, and important knowledge was obtained on mechanical engineering and plasma surface interactions. In order to understand the tritium behavior in JT-60U, tritium retention in the first wall and tritium exhausted through the pumping system were measured. These results yield useful information on the tritium behavior in a future DT fusion machine.