Recent improvements in the operation of the CTX spheromak device have produced discharges containing evidence for a pressure-driven instability. The instability leads to a distinct event in the discharge, which can be studied in detail. Data are presented which reasonably discount Taylor relaxation of the current profile as the cause of the event. The critical value of the normalized pressure gradient has been measured and is compared with the Mercier limit.PACS numbers: 52.55.Hc, 52.35.Py A spheromak is a toroidal magnetic configuration with large toroidal and poloidal plasma currents which generate most of the internal magnetic field. This configuration is attractive for a fusion reactor because it is compact, has a high level of Ohmic heating power, and thus, may not require auxiliary heating (such as neutral beam or rf injection), and has a high engineering p (pcng&P/Blaw). However, the theoretically predicted internal p (p yo \ocP/(B 2 \ 0 \) calculated with the Mercier criterion is small, ranging from « 0.2% for the "classical" spheromak 1 to (1-2)% for nonspherical cross sections, 1 " 3 to ?£7% for the spheromaks with current holes. 2 " 4 In fact, many other toroidal magnetic configurations have low predicted p limits. Tokamaks are theoretically limited by the ballooning criterion 5 to ;S(5-10)%, and reversed field pinch equilibria stable to current-driven resistive tearing modes have a predicted p limit 6 of « 20%. The experimental significance of predicted p limits is often unclear, since other effects might limit plasma performance. If the p limits could be reached, the expected plasma behavior is often unknown. Tokamaks historically have had difficulty reaching the predicted p limit, 5 but recently large tokamaks have been used to explore plasma conditions at reactor relevant p values. The highest values obtained are empirically found to follow a scaling law of the form Pmax^3I/aB On %, MA, m, and T) 7,8 ; however, this can be consistent with either ballooning mode or kink mode limits. 7 In addition, operation at this p limit is found to be disruptive 7 in some cases and in other cases a degradation of energy confinement without disruption is observed. 8 Reversed field pinches normally operate 6 with roughly constant p («10%), indicating an empirical limit, but the value is less than the predicted value, which does not include the localized resistive interchange mode (sometimes called the "g mode"). In contrast, spheromaks often have p values above those predicted. 9 ' 10 In this Letter, strong evidence for a pressure-driven instability in CTX 11 spheromaks is presented. The instability leads to a distinct event in the discharge which can be analyzed in detail. It is found that when a particular threshold value in the pressure gradient is exceeded, internal plasma is expelled toward the wall in 10-20 jus. The resulting temperature and density profiles are both hollow (about the magnetic axis), strongly indicating a magnetic flux interchange. These hollow profiles are short lived, and evolve back to mod...