Suitability Evaluation of Containment Thermal-Hydraulics Codes in Marine NPP Reactor Compartment Safety Analysis

At present, there lacks the code for the thermal-hydraulics safety analysis of the marine nuclear power plant reactor compartment. Based on the containment phenomenon identification and ranking table (PIRT) method and a reactor compartment pressure response during typical LOCA accident, the reactor compartment PIRT is established and the matching capability between the GOTHIC Codes validation matrix and PIRT is studied. Finally, the code is proved to be applicable for the safety analysis of the typical marine NPP reactor compartment. The analytical methodology is also a useful reference for the cross-domain application evaluation of the safety analysis codes for nuclear electrical field.