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.
Mahmoud Z. Youssef, Hesham Khater, Mike Kotschenreuther
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 804-809
Chamber Technology | doi.org/10.13182/FST01-A11963338
Articles are hosted by Taylor and Francis Online.
Plasma stabilization and plasma elongation are best achieved by keeping a stabilizing shell as close as possible to the plasma. In CLiFF design, a 2-cm-thick flowing liquid layer is placed in front of a solid FW and is thought to be used as an active conduction shell if its conductance is relatively high such as with liquid lithium. On the other hand, higher conductance is achieved by solid shells (e.g. Cu, Al, FS, W, V alloy). In the present study, the adverse effect of this stabilizing shell (whether it is liquid or solid material) on tritium breeding ratio (TBR) is investigated. Among the design features that quantify this effect are: the type of breeder and structure, the degree of Li-6 enrichment, the material and thickness of the shell, and whether or not there is a front beryllium multiplying zone in the blanket. Additionally, the presence of a solid conducting shell near the FW will impose a safety concern in the case of LOCA. The present study addresses this concern and comparison of the level of decay heat and waste disposal rating is made among the candidate materials for the stabilizing shell.