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 8–12, 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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
R. A. Schrack, O. A. Wasson,D. C. Larson, J. K. Dickens, J. H. Todd
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE93-A24044
Articles are hosted by Taylor and Francis Online.
Relative cross-section measurements for the 10B(n, α1γ)7Li reaction were made using the Oak Ridge Electron Linear Accelerator Laboratory neutron source. The cross sections were measured by observing the 478-keV photon using an intrinsic germanium detector. The neutron flux was monitored with a high-efficiency plastic scintillator. Monte Carlo calculations were used to provide multiple-scattering and neutron-attenuation corrections to the data. The measured cross sections differ as much as 40% from the ENDF/B-VI evaluation for incident neutron energies greater than 1.5 MeV.
