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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Carlos Gago B.
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 55-64
Technical Paper | doi.org/10.13182/NSE79-A21285
Articles are hosted by Taylor and Francis Online.
It is shown that Fick's law can be used in the calculation of the rigorous neutron slowing down length for hydrogenous moderators (or in fact for any moderator), provided that the corresponding diffusion coefficient is determined within the set of equations of the consistent P1 approximation. For a given moderator, this coefficient depends solely on lethargy and source spectrum and therefore can be evaluated prior to an actual numerical calculation, which can then be carried out within the simplicity of a diffusion approximation. Furthermore, the flux calculated in this way essentially agrees with the consistent P1 result in all regions where this approximation is justified. The practical generalization to nonhydrogenous moderators is carried out by means of the Goertzel-Greuling procedure.