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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
DOE, General Matter team up for new fuel mission at Hanford
The Department of Energy's Office of Environmental Management (EM) on Tuesday announced a partnership with California-based nuclear fuel company General Matter for the potential use of the long-idle Fuels and Materials Examination Facility (FMEF) at the Hanford Site in Washington state.
According to the announcement, the DOE and General Matter have signed a lease to explore the FMEF's potential to be used for advanced nuclear fuel cycle technologies and materials, in part to help satisfy the predicted future requirements of artificial intelligence.
Mien-Win Wu, Jen-Chang Chou
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 268-275
Technical Paper | doi.org/10.13182/NSE77-A27039
Articles are hosted by Taylor and Francis Online.
The cross section of the 58Ni(n, p)58Co reaction was determined by the activation method for neutron energies from 3 to 4.8 MeV. Neutron fluxes were measured with a laboratory-fabricated proton recoil telescope consisting of a radiator, an evacuated cell, and a surface barrier detector. The absolute efficiencies of the telescope for different neutron energies have been interpreted by Monte Carlo calculation as well as by a direct integration method. The fraction of activations induced by neutrons following single elastic scattering to those without scattering in the nickel sample was also calculated by a Monte Carlo program. The neutron attenuation through the nickel sample was also considered. Major sources of error in the cross-section determination are summarized and discussed. The total error was estimated to be 4 to 5%.