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.
Kenji Takeuchi, Michael Y. Young, Lawrence E. Hochreiter
Nuclear Science and Engineering | Volume 112 | Number 2 | October 1992 | Pages 170-180
Technical Paper | doi.org/10.13182/NSE112-170
Articles are hosted by Taylor and Francis Online.
Wallis’ flooding correlation is generalized for both small and large pipes by the use of the critical Kutateladze number. A drift flux correlation is then obtained that is tangential to the generalized flooding curve. A simple function of void fraction for the correlation parameter is sufficient to provide good agreement with steam generator test data, without using flow regime maps. After the drift flux correlation is determined with the large-pipe test, it is implemented in the TRAC-PD2 computer code to be tested against the flooding curve for a small-diameter pipe. The Chexal-Lellouche formulas are also applied to the data analysis, and the results are compared with the present correlations. Discussion is extended to the Zuber-Findlay method of data analyses for the drift velocity and the distribution parameter, in relation to the flooding curve.