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. W. Dyos, G. C. Pomraning
Nuclear Science and Engineering | Volume 25 | Number 1 | May 1966 | Pages 8-11
Technical Paper | doi.org/10.13182/NSE66-A17495
Articles are hosted by Taylor and Francis Online.
A method is given for the calculation of effective neutron cross sections for materials with grain structure. The method is particularly suited for the calculation of effective cross sections at thermal energies where the ratio of scattering to total cross section for absorbers is small. The grain shielding factors have been calculated through the 1.056-eV resonance of 240Pu for the case of 200-µ-diam plutonium oxide grains, containing 17%240Pu, homogeneously dispersed in BeO. It is shown that provided the centers of the grains are not less than 800 µ apart the method given in this paper is applicable and gives excellent agreement with the results obtained from a P1 , S8 neutron transport theory calculation.