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.
D.C. Norris, W. M. Stacey, M. Yaksh, S.M. Ghiaasiaan
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 924-929
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963731
Articles are hosted by Taylor and Francis Online.
Heat removal and heat conduction analyses were performed to determine the heat flux limits for a number of possible structural material/coolant combinations: SS316/H2O (5 and 14 MPa), HT-9/H2O (14 MPa), V-4Cr-4Ti/H2O (14 MPa), HT-9/He (15 MPa), and V-4Cr-4Ti/He (15 MPa). A common first-wall design geometry, similar to that of ITER, was used. With H2O coolant and steel, the ASME stress criteria were the most limiting, which constrained the surface heat flux to 0.46 MW/m2 (5 MPa) and 0.41 MW/m2 (14 MPa) for SS316 and to 1.1 MW/m2 for HT-9/H2O (14 MPa). The maximum Be temperature was most limiting for V-4Cr-4Ti/H2O (14 MPa), constraining the heat flux to 1.73 MW/m2. For this first wall geometry, which was optimized for H2O, the He-cooled designs were limited by the 2% pumping power constraint to less than 0.5 MW/m2.
The sensitivity of heat flux limits to maximum allowable material temperatures and to parameters of the model was evaluated.