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.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
D. Haas, J. Van de Velde, M. Gaube, J. Ketels, C. Van Loon
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 75-88
Technical Paper | Fuel | doi.org/10.13182/NT77-A31831
Articles are hosted by Taylor and Francis Online.
An experiment sponsored by the Gesellschaft für Kernforschung at Karlsruhe, by Belgonucléaire, and by Interatom was carried out in the French reactor Rapsodie from February 1971 to September 1972, in the frame of a research and development program for the fast breeder prototype reactor SNR. This experiment consisted in the irradiation of two bundles, each containing 34 mixed-oxide pins, with spacer grids and tie-rods, up to a peak burnup of 10.6 at.% and a peak total neutron fluence of 8 × 10 20 mm −2, corresponding to a peak fast fluence (E > 0.111 MeV) of 6.4 × 1020 mm−2. The postirradiation examinations showed that the cold-worked WNr. 1.4970 cladding stainless steel has a lower irradiation-induced swelling than the solution-annealed WNr. 1.4988. Important inelastic deformations of both types of claddings have been observed; the largest part of these deformations can be explained by the in-pile creep. A mechanical interaction between the fuel and the cladding is not excluded in the case of the pins with the cladding steel WNr. 1.4970. The destructive examinations emphasized the influence of the pellets’ initial stoichiometry on the fission product migration, on the plutonium radial distribution, and on the fuel-cladding chemical interaction. An interaction between the fuel and the blanket pellets, due to the cesium migration and to the formation of cesium uranates, leading to local cladding strains, has been noted. These phenomena, as well as the chemical interaction between the fuel and the cladding, have been investigated by extensive microprobe analysis. Finally, the fuel restructuration has been analyzed and interpreted as a function of the fuel characteristics, irradiation conditions, and cladding deformations.
