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.
K. Takase, M. Z. Hasan, T. Kunugi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1840-1844
Plasma-Facing Component | doi.org/10.13182/FST92-A29986
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in non-MHD laminar flow through rectangular channels in the first wall and limiter/divertor plates of fusion reactors has been analyzed numerically. Even for uniform heat flux, the Nusselt number (Nu) is not constant along the face of a rectangular channel, because the velocity is much smaller near a corner. For uniform heat flux, Nu varies by 67% from the center of a side to the corner (6.7 to 2.2). Therefore, the corners of a rectangular channel are possible hot-spot areas of concern for thermal-hydraulic designs. In addition, the surface heat flux on coolant channels in the plasma-facing components varies circumferentially. This nonuniformity of surface heat flux also affects the Nu. At the center of a side, Nu can be reduced from 6.7 to 2.8, i.e. by about 58%. For large nonuniformity of surface heat flux, the Nu at some locations can become infinity or negative; infinity, when the coolant/wall interface temperature becomes equal to the coolant bulk temperature and, negative, when the bulk temperature becomes larger than the interface temperature at these locations. The entry length is also increased due to the nonuniformity of surface heat flux. This increase can be as much as 4 times the entry length for uniform heat flux. For safe thermal-hydraulic designs of the first wall and limiter/divertor plates of fusion reactors, these effects must be taken into consideration.