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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
C. Y. Fu
Nuclear Science and Engineering | Volume 106 | Number 4 | December 1990 | Pages 494-500
Technical Note | doi.org/10.13182/NSE90-A23774
Articles are hosted by Taylor and Francis Online.
The ENDF/B-V differential cross sections for neutron scattering from natural carbon below 2 MeV, recommended as standards for measurements and based on an R matrix analysis for 12C using natural carbon data, are revised to include 13C resonances for high-resolution applications. The recommended 13C cross sections are also based on an R matrix analysis of the available data. The 0.1529- and 1.736-MeV resonances rise above the natural carbon background by 7 and 1%, respectively. The angular distributions of the elastically scattered neutrons from 13C are generated by the R matrix theory. The final recommended cross sections and Legendre coefficients of angular distributions for natural carbon, adopted for ENDF/B-VI, are tabulated.