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.
Pekka Jauho, Antti Virjo
Nuclear Science and Engineering | Volume 31 | Number 1 | January 1968 | Pages 102-109
Technical Paper | doi.org/10.13182/NSE68-A18012
Articles are hosted by Taylor and Francis Online.
A nonabsorbing heavy-gas model is used to study neutron thermalization in a moderator with a nonuniform temperature distribution. The method of Williams is first extended to arbitrary temperature distributions. The method is then applied to spherical geometry and numerical results are given for the mean energy of the neutrons. In the case where the radius of curvature of the temperature discontinuity is of the same order of magnitude as the rethermalization length, new transport-theoretical corrections are required to diffusion-theoretical results. In plane geometry, the P3 approximation is used to solve the Boltzmann equation and the mean energy of neutrons is calculated. Results are compared with diffusion-theoretical and exact calculations and agreement with the latter is found to be very satisfactory. Some neutron spectra are also plotted in the P3 approximation.