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.
T. W. T. Burnett and T. G. Williamson
Nuclear Science and Engineering | Volume 21 | Number 2 | February 1965 | Pages 201-205
Technical Paper | doi.org/10.13182/NSE65-A21044
Articles are hosted by Taylor and Francis Online.
The infinite multiplication factor, k∞ is one of the basic parameters of a sub-critical assembly. Usually, these assemblies are designed for maximum k∞ however, it is difficult to conduct laboratory experiments which yield a value of k∞ to reasonable accuracy. Common methods, such as the loading technique and exponential experiment, are of doubtful validity or require apparatus not always available. Pulsing techniques are widely accepted, but are difficult to apply to reflected assemblies. In this work, an alternative approach is used. It is based on the integration of the thermal-neutron flux over the equivalent infinite medium. Use of variations in the method with poisoned assemblies eliminates the need for accurate determinations of the source strength, the absolute thermal-flux calibration, and the epithermal parameters of the medium. The theory is general and can be applied with a minimum of equipment. The results obtained from this method (and its variations) were checked by pulse measurements on the bare assembly and by a four-factor formula calculation. All results agree to within 2%.