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.
Ehsan U. Khan
Nuclear Science and Engineering | Volume 61 | Number 1 | September 1976 | Pages 112-115
Technical Note | doi.org/10.13182/NSE76-A28467
Articles are hosted by Taylor and Francis Online.
The relative importance of energy redistribution by thermal conduction and sweep flow mixing in a wire-wrapped fuel assembly are quantitatively described at various Reynolds numbers. For a given bundle geometry, a critical Reynolds number exists below which thermal conduction appears to govern the temperature distribution within the bundle. As the thermal conduction effects become progressively important at low Reynolds numbers, the transverse temperature gradient in the bundle decreases. This result would have an important effect on incoherency in assembly voiding. If one were to develop a model of a full-size liquid-metal fast breeder reactor bundle to study incoherency in voiding, an important parameter is the maximum temperature difference at the bundle exit. Whereas this parameter is the same for a 19- and 217-pin bundle at design operating conditions, it is significantly different at low Reynolds numbers. This low Reynolds number bundle-size effect was determined by analysis of steady-state data and is valid for very slow transients where the thermal inertia of the structure is unimportant. Inclusion of the structure thermal inertia would tend to diminish this bundle-size effect.