Science and Technology of Nuclear Installations / 2012 / Article / Fig 22

Research Article

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

Figure 22

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).

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