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. A. Karam, W. Y. Kato
Nuclear Science and Engineering | Volume 52 | Number 2 | October 1973 | Pages 201-208
Technical Paper | doi.org/10.13182/NSE73-A28189
Articles are hosted by Taylor and Francis Online.
Systematic errors responsible for the large discrepancy between the measured and calculated central reactivity coefficients were examined. These errors were narrowed to two sources: the normalization integral (or perturbation denominator) and the conversion factor of inhour, or dollars, to Δk/k units. The magnitude of both sources of error is uniquely determined by the ratio of the measured-to-calculated normalization integral when the measurement is carried out using the 252 Cf source-reactivity method. The measured-to-calculated normalization integral ratios for ZPR-6 Assemblies 6A and 7, two typical demo-plant-size Liquid Metal Fast Breeder Reactor criticals, were 1.19 and 1.21, respectively. The magnitude of this discrepancy is essentially the same as that found for the central reactivity coefficient. Analysis of the available fission rate distribution in both assemblies indicates that the calculated normalization integral may be underestimated by 6 to 8% and that the remainder of 10 to 14% must come from the conversion factor. The delayed-neutron data of Krick and Evans, when used with the appropriate average number of neutrons per fission in each assembly, yield conversion factors 9 to 13% higher than the delayed-neutron data of Keepin. This would provide the explanation of the central reactivity discrepancy. Unfortunately, the method of calculating βeff could also produce errors of this magnitude even if one has an absolutely correct set of delayed-neutron fractions. More definitive measurements of the delayed-neutron fractions of pertinent isotopes, as a function of the incident neutron energy, are needed. In addition, measurements of βeff in various assemblies by different methods are required.