The fusion performance of ELMy H-mode DT plasmas with q95 = 3 and
\\beta_N = 1.8 (also referred to as medium-\\beta_N baseline scenario in the rest of this paper)
are predicted with the JINTRAC suite of codes and the QuaLiKiZ transport model.
The predictions are based on the analysis of DT plasmas from the first DT campaign
on JET in 1997 (DTE1) and pure deuterium plasmas developed at JET in preparation
for the DT experimental campaign in 2021 (DTE2), after the installation of a Be/W
ITER-like wall (ILW) in 2011.
The sensitivity of the predictions to plasma parameters such as current, toroidal
field, pedestal confinement and impurity content are analysed together with the
sensitivity to the amount of auxiliary heating power available.
The simulations indicate that a fusion power of 10 MW should be achievable under
a fairly wide range of assumptions, provided that the auxiliary heating power is around
or above 38 MW. Higher fusion power approaching 15 MW could be achievable for this
value of  \\beta_N only for particularly pure plasmas and with 40 MW of additional heating
power.