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

<div>Coolant behavior during SBO transient with loss of primary coolant and AM measure [<a href="/journals/stni/2018/7635878/#B14">11</a>].</div>

Science and Technology of Nuclear Installations

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Figure 1: 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 1 | 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 