Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 581-585
Blanket and First-Wall Engineering / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40101
Articles are hosted by Taylor and Francis Online.
The ATHENA code is being developed by EG&G Idaho as a general purpose thermal hydraulics code for safety transient analysis of fusion reactors. This report documents the use of ATHENA to model a lithium-lead cooled fusion reactor design. The code models the MHD effects resulting from the flow of a conducting fluid through a strong steady magnetic field. The code performed well within the range of available lithium-lead properties. The results from calculations of several operational transients and a loss of pumping power are reported.