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
Fusion Science and Technology
October 2025
Latest News
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
D. Rochman, M. Herman, P. Oblozinský, M. Sin
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 280-293
Technical Paper | doi.org/10.13182/NSE06-A2633
Articles are hosted by Taylor and Francis Online.
Neutron-induced fission cross sections for eight americium isotopes (A = 239 to 244) are predicted with the nuclear reaction model code EMPIRE-2.19. The code incorporates advanced fission modeling, presented by describing the implementation of barrier penetration, transmission mechanism, and decay probabilities. The fission cross-section calculations for americium isotopes are compared to experimental data and evaluations from the ENDF/B-VI.8, JEFF-3.1, JENDL-3.3, or preliminary ENDF/B-VII libraries when available. An analysis of the first and second fission barrier heights validates the existing systematic trend for odd and even neutron numbers.
