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.
R. Gwin, L. W. Weston, G. de Saussure, R. W. Ingle, J. H. Todd, F. E. Gillespie, R. W. Hockenbury, R. C. Block
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 25-36
Technical Paper | doi.org/10.13182/NSE71-A20342
Articles are hosted by Taylor and Francis Online.
The neutron absorption and fission cross sections for 239Pu have been measured simultaneously over the neutron energy range from 0.02 eV to 30 keV. These cross sections were measured using an ionization chamber containing 239Pu. The differential cross sections derived from these measurements are presented along with a multilevel analysis of the data up to 100 eV. A reevaluation of data obtained using a metal foil of 239Pu has also been made. Average values of the neutron capture and fission cross sections are presented for 239Pu as obtained using the ionization chamber as well as with the metal foil. A detailed comparison of the present data is made with the results of the ENDF/B evaluation for 239Pu (material 1104). The neutron cross sections presented in this report supersede the results reported previously by the authors of this report.
