反应堆一回路系统优化设计方案的可行性验证

采用优选运行参数和结构参数的方法，可达到降低核动力装置尺寸的目的。在优化设计方案投入制造前，有必要研究其在设计基准事故下的响应特性，以检验优化方案的可行性。采用RELAP5/MOD3.2程序研究现有一回路系统优化方案在完全失去厂外电、主给水丧失和小破口失水事故下的响应特性，并将安全设计准则参数与母型对比。结果表明：针对所研究的3种设计基准事故，优化方案各主要安全准则参数满足设计要求；优化方案可成功抵御这3类设计基准事故。

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.