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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
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.
