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.
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 356-365
Technical Paper | doi.org/10.13182/NSE76-A26921
Articles are hosted by Taylor and Francis Online.
The 241Am neutron absorption cross section, which is predominantly capture, has been measured from 0.01-eV to 370-keV neutron energy. The Oak Ridge Electron Linear Accelerator was used as the source of pulsed neutrons. Resonance parameters have been derived for the data up to 50 eV. The capture gamma-ray detector used was the “total energy detector,” which is a modification of the Moxon-Rae detector. This detector required that the events be weighted by their pulse height in the detector and that the net efficiency of the detector be low. The cross section was normalized at thermal-neutron energies (0.02 to 0.03 eV), and the shape of the neutron flux was measured relative to the 10B(n, α) cross section up to 2 keV and relative to the 6Li(n, α) cross section at higher neutron energies. The results of the measurement indicate a lower cross section (∼25%) between 0.3 and 100 eV than has been previously indicated and an appreciably higher cross section (by 100% at 100 keV) from 20 to 370 keV.