An emerging issue relative to beryllium technology in fusion involves triti
um interactions with molten beryllium-bearing salts. Innovative designs for
fusion reactors, both magnetic and inertially confined, feature the molten
salt mixture 2LiF . BeF2, commonly called Flibe, as a tritium breeder and
coolant. Tritium is bred in the Flibe as neutrons from the plasma are absor
bed by Li atoms, which then transmute to tritium and helium. Transmutation
of tritium from Be also occurs. Among the issues to be resolved for such co
olant systems is the potential loss of tritium from the Flibe coolant to th
e walls of the system, particularly through heat exchanger tubes, and from
there into secondary coolants or working fluids and the environment. Effect
ively removing tritium from Flibe in clean-up units is also important.
In quiescent or low Reynolds number flow, tritium movement through Flibe is
governed by diffusion. For Flibe in turbulent flow, as in heat exchanger t
ubes, transport is by turbulent mixing, and the same flow conditions and st
ructural design features that maximize heat transfer to the heat exchanger
walls will enhance the transport of tritium to those same surfaces. Analyse
s have been performed to estimate the fractional loss of tritium through he
at exchanger tubes and release rates from Flibe droplets in vacuum disengag
ers in molten Flibe systems. The calculations suggest unacceptably large lo
sses of tritium through heat exchanger tubes. The gravity of the implicatio
ns of these estimates calls for experimental verification to determine if t
ritium losses through molten Flibe heat exchangers or other Flibe systems c
an really be so high and whether vacuum disengagers will really work. There
is also a need for better information on evolution of tritium from Flibe d
roplets in a vacuum.
Several experiments are presently being planned to address these issues and
are discussed. These include experiments to induce tritium in Flibe using
spontaneous fission neutrons, experiments in flowing loops to evaluated tri
tium losses through heat exchanger walls, and exploration of schemes for tr
itium extraction from molten Flibe.