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.
M. Hayashi, T. Nishigori, R. G. Alsmiller, Jr., R. A. Lillie
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 391-400
Technical Paper | doi.org/10.13182/NSE91-A23864
Articles are hosted by Taylor and Francis Online.
Calculational studies are conducted of neutron and gamma-ray transport in the beam tubes of a proposed high-flux reactor for the Advanced Neutron Source. To avoid excessively long computing times, the calculations were carried out by coupling two, two-dimensional discrete ordinates calculations. The calculational methodology used is briefly described. Calculated results are presented of the thermal neutron, nonthermal neutron, and gamma-ray fluxes in a radial and a tangential beam tube. Both scalar and angular fluxes in and at the exit of the beam tubes are given. When compared with the radial beam tube, the tangential beam tube shows a lower flux of high-energy neutrons and a much lower flux of gamma rays. The spectral characteristics of the particle fluxes at the exits of the beam tubes are similar to those at the entrances.