ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
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.
D. A. Niebruegge, E. L. Tolman, C. W. Solbrig
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 363-368
Technical Note | doi.org/10.13182/NSE78-A27316
Articles are hosted by Taylor and Francis Online.
Thus far, existing computer programs have been adequate to predict the behavior of the loss-of-fluid test facility (LOFT) non-nuclear loss-of-coolant experiments. The work presented here describes a predictive capability for modeling nuclear experiments to determine if the same fuel can be used in several experiments. This is analogous to determining if fuel may be reused after a pressurized water reactor loss-of-coolant accident. We are concerned here with discussing only best-estimate calculations for experimental predictions and not the conservative models used for licensing. It was found that an adequate analysis procedure could be established by modeling accurately the fuel stored energy before the experiment is initiated. The initial stored energy in the fuel was found to be the most important fuel rod parameter influencing the maximum cladding temperature obtained in the transient.