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.
G. R. Odette, T. O. Ziebold
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE72-A22528
Articles are hosted by Taylor and Francis Online.
An experiment was performed to measure the energy-dependent damage function for the neutron irradiation induced increase in the lower yield strength of iron. Small tensile test specimens were exposed at low temperatures (<100°C) to 1017 - 1018 n/cm2 (E > 1 MeV) in seven reactor spectra while a high degree of consistency among all other variables known to be significant was maintained. The neutron flux spectra in all locations were measured using the multiple foil activation technique and the SAND-II code for the data analysis. The mechanical property and flux spectral data were then analyzed using SAND-II to unfold the damage functions. Estimates of errors induced in the solution by the iterative unfolding procedure were made considering possible contributions from both the lack of mathematical solution uniqueness and data error propagation.