Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal-Hydraulic System Analysis Code

Figure 13

(a) Changes in the heat transfer mode at S240–2 per the applied CHF correlation; (b) the repeated transitions between nucleate boiling and transition boiling in the flow oscillation phase; (c) abrupt rise of the exterior surface temperature at S240–2 predicted when the SULTAN correlation was applied.