RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation

<table>LSTF results for cladding surface temperature, collapsed liquid levels in upper plenum, core, and upflow side of SG U-tubes and primary mass flow rate in loop with PZR (22400 to 24200 s).</table>

Science and Technology of Nuclear Installations

fig22

Figure 22

Figure 22: RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation 