100 kWe级空间快堆核电源系统仿真平台开发与应用

空间核反应堆电源作为一种具有竞争力的空间电源方案,正逐渐受到关注及应用。本文针对一个100 kWe级锂冷快堆耦合布雷顿循环的空间堆核动力系统方案,修改了RELAP5程序中的物性程序、换热模型,程序中的中子动力学模块使用蒙特卡洛方法计算快堆物理参数与堆芯控制调节参数,由此集成并建立一个空间快堆核动力系统综合仿真平台,应用该平台对100 kWe级空间堆核动力系统进行了稳态模拟与事故分析。结果表明:在瞬态发生后系统各参数变化符合预期,验证了各部件及控制系统的功能性及有效性;同时,还初步进行了仿真平台用于100 kWe级空间反应堆核动力系统设备的设计优化的实践,为空间快堆设计与安全分析提供了技术储备。

Development and Application of a Simulation Platform for 100 kWe Space Fast Reactor Nuclear Power System

As a competitive space power supply scheme, space nuclear reactor power supply is getting more and more attention and application. In this paper, the physical property part and heat transfer mode of the RELAP5 program are modified for the analysis of a 100 kWe space reactor nuclear power system scheme for lithium-cooled fast reactor coupled with Brayton cycle.The thermodynamic and transport properties of lithium liquid and He-Xe mixture gas are applied to the RELAP5 code. The neutron kinetics module uses the Monte-Carlo method to calculate the physical, control,and regulation parameters of the fast reactor. The platform is applied in both the steady-state simulation and the safety analysis for the 100 kWe space reactor nuclear power system. The results indicate that the parameters of the system are in accordance with the expectation after the transient state occurs, verifying the functionality and effectiveness of the components and control system. Meanwhile, applications of the simulation platform to the design optimization of 100 kWe space reactor nuclear power system devices have also been gradually carried out, which provides technical reserves for the design and safety analysis of space fast reactor.