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.
James M. Wu, Chun-Fa Chuang
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 40-49
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33301
Articles are hosted by Taylor and Francis Online.
Three-dimensional natural convection of the compacted spent fuel rod in a pool was studied. A numerical technique was developed based on the conservation of mass, momentum, and energy of a typical flow element in the channel. The coolant flow is laminar and single phase. The decay heat generation from the spent fuel rod was assumed to be a chopped sine curve. Different configurations of the fuel rods were considered. Calculation was done by varying the inlet coolant temperature, decay heat generation, radius of the spent fuel rod, and distance between spent fuel rods. A simple correlation for the Nusselt number, hydraulic diameter, Prandtl number, and Grashof number was obtained.