  The role of flux-limited thermal conduction on the fusion performance of the
uniaxially-driven targets studied by Derentowicz et al. [1] is explored as part
of a wider effort to understand and quantify uncertainties in ICF systems
sharing similarities with First Light Fusion's projectile-driven concept. We
examine the role of uncertainties in plasma microphysics and different choices
for the numerical implementation of the conduction operator on simple metrics
encapsulating the target performance. The results indicate that choices which
affect the description of ionic heat flow between the heated fusion fuel and
the gold anvil used to contain it are the most important. The electronic
contribution is found to be robustly described by local diffusion. The
sensitivities found suggest a prevalent role for quasi-nonlocal ionic
transport, especially in the treatment of conduction across material interfaces
with strong gradients in temperature and conductivity. We note that none of the
simulations produce neutron yields which substantiate those reported in Ref.
[1], leaving open future studies aimed at more fully understanding this class
of ICF systems.
