ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using Steam Generator Secondary-Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water

<table class="figure-group"><tr class="fig-image" id="a"><td><object data="https://static.hindawi.com/articles/stni/volume-2016/7481793/figures/7481793.fig.0021a.svgz" name="7481793.fig.0021a" type="image/svg+xml"></object></td></tr><tr class="fig-caption"><td><b>(a) </b>Overall transient (0–2800 s)</td></tr><tr class="fig-image" id="b"><td><object data="https://static.hindawi.com/articles/stni/volume-2016/7481793/figures/7481793.fig.0021b.svgz" name="7481793.fig.0021b" type="image/svg+xml"></object></td></tr><tr class="fig-caption"><td><b>(b) </b>Local transient (800–2800 s)</td></tr></table>

<div>LSTF and RELAP5 results for primary and SG secondary pressures in loop-A in case of no release of dissolved gas.</div>

Science and Technology of Nuclear Installations

fig21

Figure 21

Figure 21: ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using Steam Generator Secondary-Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water 

Figure 21 | ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using Steam Generator Secondary-Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water 