A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident

<div>The corium heat loss to concrete in the cases with/without cavity flooding.</div>

Science and Technology of Nuclear Installations

Figure 19: A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident 