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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Nuclear Science and Engineering
February 2025
Nuclear Technology
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Latest News
IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
J. Mennig, J. T. Marti
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 365-368
Technical Paper | doi.org/10.13182/NSE68-A17580
Articles are hosted by Taylor and Francis Online.
A semi-analytical method for solving the monoenergetic transport equation with isotropic scattering in plane geometry is developed, in which the slab system is subdivided into a number of discrete space points in x, while the angular variable is treated analytically. This is equivalent to taking N to ∞ in SN theory and avoids the numerical instabilities inherent in the limiting process. General boundary conditions are introduced allowing finite multilayer slabs, cells, and shielding problems with specified incident angular distribution of neutrons to be handled by the same formalism. Analytical expressions are derived for the angular distributions, and fluxes are obtained by solving a matrix problem, where the matrix elements are integrals over rational functions of the angular variable. Computing times are comparable to low-order SN calculations.