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.
H. Tellier
Nuclear Science and Engineering | Volume 79 | Number 4 | December 1981 | Pages 393-403
Technical Paper | doi.org/10.13182/NSE81-A21390
Articles are hosted by Taylor and Francis Online.
Until now, there has been a discrepancy between the computed and the measured values of the 238U effective capture integral. The former has always been greater than the latter. For this reason, the reactor physicists have used an adjustment of the computed value. At the present time, the accuracy of the cross-section knowledge has increased, and the reactor computation codes are almost exact. Such an adjustment, therefore, is no longer justified. Recently, several new measurements of the resonance parameters were carried out and the use of a multilevel formalism was suggested to compute the 238U cross sections. This paper shows that the simultaneous use of recent parameters and the Reich-Moore formalism explain the discrepancy. For thermal neutron reactors, and depending on the neutron spectrum hardness, between one-half and two-thirds of this discrepancy is explained by the neutron data and the remainder by the multilevel formalism. This last effect is not negligible. We have done similar studies for 232Th, but in this latter case the multilevel effect was found to be much smaller than for the 238U and can be neglected in most applications.