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.
Joseph C. Stachew
Nuclear Technology | Volume 4 | Number 4 | April 1968 | Pages 206-216
Technical Paper and Note | doi.org/10.13182/NT68-A26318
Articles are hosted by Taylor and Francis Online.
The uranium and plutonium isotopic distributions of 45 irradiated fuel rods of natural uranium dioxide are compared to theoretical predictions made using three-dimensional P-1 neutron diffusion techniques. The calculations are different in that normalization to experimental results is made only by use of the total core energy output and measured critical rod-bank heights. This is in contrast to normalizing each individual fuel-rod burnup to the experimental value and then investigating resultant isotopic distributions in the rod. The comparison indicates good agreement but identifies the need for a spatial spectrum variation of the 238U epithermal resonance absorption cross section and improved time -dependence of the 238U and 239Pu cross sections.