Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1

<div>Research nuclear reactor (VVR): 1–tank; 2–fuel assembly (FA); 3–beryllium reflector; 4–reactor vessel; 5–7–baffle, guiding, and support grids; 8, 9–suction and pressure pipelines [<a href="/journals/stni/2021/9423176/#B5">5</a>].</div>

Science and Technology of Nuclear Installations

fig1

Figure 1

Figure 1: Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1 

Figure 1 | Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1 