Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System

<div>Comparison of circumferential stress estimations from PTS transient based on direct coupling and sequential coupling-simulation methods (SC – sequential-coupling method and DC – direct-coupling method).</div>

Science and Technology of Nuclear Installations

fig13

Figure 13

Figure 13: Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System 

Figure 13 | Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System 