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.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
Michael S. Milgram
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 249-269
Technical Paper | doi.org/10.13182/NSE78-A27304
Articles are hosted by Taylor and Francis Online.
The integral transport equation for the flux density in the interior of an infinite homogeneous cylinder is reduced to a matrix eigenvalue problem for the critical cylinder and a set of linear algebraic equations for the driven case with surface in-currents. The matrix elements are identified as moments of modified Bessel functions and are easily computed. A connection is made with classical diffusion theory via a related matrix eigenvalue problem, from which the diffusion coefficient and extrapolation endpoint can be computed. Analytic properties of the matrix elements are used to obtain approximate solutions for (optically) dense and transparent cylinders. Numerical results are given for the American Nuclear Society benchmark black rod problem, and the fact that only small matrices are required for a large range of problems is demonstrated.