Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

<div>Normalized assembly power distribution before the accident (a) and at core maximum power (b) during the CRDA of control rod 15.</div>

Science and Technology of Nuclear Installations

Figure 11: Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics 