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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
High temperature fission chambers engineered for AMR/SMR safety and performance
As the global energy landscape shifts towards safer, smaller, and more flexible nuclear power, Small Modular Reactors (SMRs) and Gen. IV* technologies are at the forefront of innovation. These advanced designs pose new challenges in size, efficiency, and operating environment that traditional instrumentation and control solutions aren’t always designed to handle.
Renato Bobone
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 337-353
Technical Paper | doi.org/10.13182/NSE67-A17281
Articles are hosted by Taylor and Francis Online.
The solution of a multidimensional, many-region boundary value problem is expressed, in each region, by a truncated, rapidly convergent series of functions that are solutions of the partial differential equation in the given region, i.e., “solution-functions”. The eigenvalues and the corresponding eigenfunctions of the problem are then found by a least mean square method. This scheme is applied by means of a computer to the calculation of eigenvalues and eigenfluxes in the diffusion approximation of a nuclear reactor of cylindrical geometry.