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. J. Perkins, N. Evans, Malcolm C. Scott, B. Y. Underwood
Nuclear Science and Engineering | Volume 78 | Number 1 | May 1981 | Pages 30-43
Technical Paper | doi.org/10.13182/NSE81-A19604
Articles are hosted by Taylor and Francis Online.
A miniature NE-213 scintillation counter and hydrogen proportional counters have been used in conjunction with a calibrated 14-MeV deuterium-tritium neutron source to measure the neutron flux per source neutron per second at a number of positions in a 1.25-m-diam sphere of lithium fluoride. The experimental techniques used are discussed, and the resulting neutron spectra are compared with those from one-dimensional Sn calculations using the ENDF/B-IV data set, allowance being made both for neutron yield anisotropy and for the variation in source neutron energy with angle of emission.