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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.
Lowell H. Holway, Jr.
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 191-201
Technical Paper | doi.org/10.13182/NSE59-A25659
Articles are hosted by Taylor and Francis Online.
The multigroup diffusion equations are solved formally by expanding the flux in each group in a series of eigenfunctions of the scalar Helmholtz equation. The resulting secular determinant is complicated, but a perturbation solution may be developed for the coupled multigroup equations. In the case of one energy group, the perturbation method chosen reduces to a formula simpler to use and more rapidly convergent than the Rayleigh-Schroedinger formulas. An operator convenient for expressing the boundary conditions at an interface in multiregion reactors is defined. The foregoing techniques are applied to the Fermi age equation for a reflected reactor. Numerical examples are given to illustrate the rates of convergence in typical reactor design problems.