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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
P. Ihle
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 206-219
Technical Paper | doi.org/10.13182/NSE84-A18578
Articles are hosted by Taylor and Francis Online.
The results of flooding experiments with blocked arrays (FEBA) are presented, a program performed at Kernforschungszentrum Karlsruhe within the framework of the Project Nuclear Safety (PNS). Experiments performed out of pile show that coolant channel constrictions of up to 90% do not lead to significant core coolability problems during reflood. This is even true for low water injection rates corresponding to a flooding velocity of 2 cm/s for the cold bundle. The results of the thermal-hydraulic experiments cover rather widely the cladding temperature range below 1000°C. However, outlining the total range of heat transfer conditions in severely damaged rod bundle geometries, investigations performed within the framework of the PNS are mentioned as well. They provide information about the condition of rod bundles being exposed to temperatures of up to 2000°C prior to reflood.