Feasibility Test for Reactor Coolant System Optimized Design Scheme

The size of a nuclear component could be reduced by optimum selections of the operational and structural parameters. Before an optimized design scheme is manufactured, it is necessary to obtain its transient behaviors and verify its feasibility under design basis accidents. In this work, the RELAP5/MOD3.2 code was employed to simulate the transient characteristics of a proposed optimized scheme under the complete loss of off-site power, loss of feedwater and small break loss of coolant accidents, and the safety criteria were compared with the prototype reactor design. The simulation results indicate that the safety criteria of the optimized scheme satisfy the design requirements, and the safety of the optimized scheme can be guaranteed in those three accidents.