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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
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%.