Investigation of Loss of Feedwater (LOFW) Accident in the APR-1400 Using Fault Tree Analysis

<div>APR1400 reactor coolant system configuration [<a href="/journals/stni/2022/4666161/#B7">7</a>].</div>

Science and Technology of Nuclear Installations

Figure 1: Investigation of Loss of Feedwater (LOFW) Accident in the APR-1400 Using Fault Tree Analysis 