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
Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Ryan Hunt, Hongjie Zhang, Alice Ying, Michael Ulrickson
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 354-358
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12379
Articles are hosted by Taylor and Francis Online.
This research reveals the results of a thermo-mechanical stress analysis of the beryllium and CuCrZr components of the Enhanced Heat Flux (EHF) First Wall (FW). Under the EHF thermal load, differential thermal expansion at the Be/CuCrZr interface can potentially lead to failure of the beryllium tiles. We have shown that the stress profile in both beryllium and CuCrZr can be improved by reducing the dimensions of the beryllium tiles covering the FW panels.In addition, our research investigated a failure condition for the FW finger's design. Specifically, we assessed the temperature profile at the CuCrZr/water interface of the EHF FW finger in the event of a single failed tile. This was done in order to determine whether or not the critical heat flux condition occurs in the coolant channel after a single tile failure. Assuming the failure of a single tile between 11.75mm and 50mm in size, temperature profiles were generated assuming flat, rectangular water cooling channels. It was found that tile failure from the edges of the finger resulted in considerably higher temperatures than tile failures at the middle of the finger. Failure of a tile along the edge of the finger may cause catastrophic failure, as the critical heat flux condition occurred at the CuCrZr/water interface even for tiles as small as 11.75mm in size.