[en] Goal was to develop a scaling expression which adequately describes profiles in existing tokamaks and which could be used to predict plasma profile shapes and magnitudes for future devices (such as ITER and TPX) without the need for a plasma transport model. This paper presents a multi-machine feasibility study of this goal. We present an initial assessment of an effort to derive an empirical expression for the normalized plasma electron temperature and electron density profile in terms of global quantities. (Global variables were used since they allowed a large enough database to be assembled for this statistical study.) Data from both JET and DIII-D were obtained in a single-null configuration with an expanded boundary divertor. The density profile parameterization indicates that as the plasma current is increased, the n_e profile broadens and the edge gradient increases; this is consistent with JET and DIII-D operations. The T_e profile broadens as the RF power is deposited farther off-axis. For both T_e and n_e profiles, the DIII-D profiles are more peaked than the JET profiles. The probable ITER profiles are discussed. 3 figs