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.
Ernest R. Venerus and M. Necati Ozisik
Nuclear Science and Engineering | Volume 26 | Number 1 | September 1966 | Pages 122-130
Technical Paper | doi.org/10.13182/NSE66-A17195
Articles are hosted by Taylor and Francis Online.
Deposition of fission products from an isothermal laminar gas stream to the surfaces of a circular tube is theoretically investigated for a source releasing a radioactive precursor into the gas stream at a uniform rate at the origin. A slug velocity profile is assumed. In solving the partial differential equations of the problem, two different models are examined as boundary conditions to couple the equations. The first model, which is referred to as the Resistance Model, is applicable when the surface concentration of the deposited precursor is small or removal of particles from the surface is negligible; and it is equivalent to assuming a fictitious unknown resistance to mass transfer at the wall surface. The boundary value problem of mass transfer based on the resistance model has been solved for the transient conditions and analytical relations are derived for the concentration of fission products in the gas stream and on the tube surface. In the second model, which is referred to as the Transport Model, a more detailed account is taken of the actual physical transport process in the immediate vicinity of the conduit surface. The removal of precursor from the surface is related to the adsorption energy of the precursor and the temperature of the surface. Removal from the gas stream in the immediate vicinity of the conduit surface is described by a stream removal coefficient which is obtained from the kinetic theory of gases. The boundary value problem based on the transport model has been solved for the steady state condition only. The transport model has been applied to experiments on deposition of radioactive isotopes from laminar gas streams and adsorption energies for some radioactive isotopes are determined. Correlation of the transport model with experiments provides a useful means for obtaining the adsorption energies of radioactive isotopes on metal surfaces.