ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow

<table class="figure-group"><tr class="fig-image" id="a"><td><object data="https://static.hindawi.com/articles/stni/volume-2018/7635878/figures/7635878.fig.0024a.svgz" name="7635878.fig.0024a" type="image/svg+xml"></object></td></tr><tr class="fig-caption"><td><b>(a) </b>Overall transient (0–16000 s)</td></tr><tr class="fig-image" id="b"><td><object data="https://static.hindawi.com/articles/stni/volume-2018/7635878/figures/7635878.fig.0024b.svgz" name="7635878.fig.0024b" type="image/svg+xml"></object></td></tr><tr class="fig-caption"><td><b>(b) </b>Local transient (2000–16000 s)</td></tr></table>

<div>TR-LF-16 test and RELAP5 results for primary and SG secondary-side pressures in loop A.</div>

Science and Technology of Nuclear Installations

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Figure 24

Figure 24: ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow 

Figure 24 | ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow 