Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code

• 3D power distribution of SMR core has been obtained by NK/TH coupling approach.
• Safety analyses were performed by coolant flow blockage or loss of flow accident.
• The verification studies were done by comparative approach of NK/TH and Relap5 code.
• The simulated results from both analyses give the accuracy of research.

This paper deals with the comparison and safety studies of the neutron kinetics and thermal hydraulic coupling analysis of small nuclear reactor core. In this study, first the coupling between neutron kinetics and thermal hydraulics has been achieved for the small nuclear reactor core. The coupling approach is done by using the lattice physics code (HELIOS), neutron kinetic code (REMARK) and thermal hydraulic code (THEATRe). After finalizing the NK/TH coupling, power distribution of reactor core has been acquired. The loss of flow accident or coolant blockage accident is considered for the safety analysis of the reactor core. The comparison studies were accomplished by comparing the results from coupled codes (HELIOS, REMARK & THEATRe) and thermal hydraulic system code RELAP5. The simulated results from both codes agree well conforming the accuracy of the NK/TH coupling approach. The purpose of the research is to corroborate the NK/TH coupling by safety pre-assessment of nuclear reactor core.