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.
A. PAZY
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 29-36
Technical Paper | doi.org/10.13182/NSE63-A26261
Articles are hosted by Taylor and Francis Online.
The present paper deals with the calculation of the thermal flux in the moderator of a supercell containing several fuel and control elements. It is assumed that the one group diffusion equation with a constant source holds in the moderator. It is further assumed that the absorption of thermal neutrons in fuel rods (or control rods) may be described as due to a cylindrically symmetric line sink. With these assumptions the diffusion equation is solved and a general expression for the thermal flux in the moderator is obtained. This expression is then used to calculate the thermal utilization in the supercell, and the ratios of absorption rates in the different elements of the lattice. General expression for the flux ratios and thermal utilization are obtained. By way of illustration, solutions of two typical cases of complex lattices are given