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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
American Fuel Resources requests license for N.M. uranium deconversion plant
American Fuel Resources, a provider a nuclear fuel cycle solutions headquartered in Spokane, Wash., has submitted an application to the Nuclear Regulatory Commission requesting transfer of a materials license from Idaho-based radioisotope manufacturer International Isotopes for a depleted uranium hexafluoride (DUF6) deconversion plant in Lea County, N.M.
Z. F. Kuang, I. Pázsit
Nuclear Science and Engineering | Volume 136 | Number 2 | October 2000 | Pages 305-319
Technical Note | doi.org/10.13182/NSE00-A2161
Articles are hosted by Taylor and Francis Online.
Recently, analytical formulas have been derived for the Feynman- and Rossi-Alpha measurements in accelerator-driven systems. In such systems, due to the multiplicity of the sources, the Feynman- and Rossi-Alpha formulas contain additional terms as compared with the traditional cases. A numerical evaluation of these formulas for systems with such sources is given. An assessment of the contribution of the terms that are novel as compared to the traditional formula is made. These include the terms arising from the source multiplicity, and the prompt-delayed and delayed-delayed correlations. Further, the consequences of averaging the delayed-neutron families are analyzed. Finally, a comparison is made, assuming traditional core material and one possible type of future accelerator-driven system.