兆瓦级高效紧凑型核动力系统运行特性研究  

Operation characteristics of a megawatt nuclear power system with high efficiency and compactness

作　　者：张明辉[1] 苟军利[1] 王政 单建强[1] ZHANG Minghui;GOU Junli;WANG Zheng;SHAN Jianqiang(School of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an 710049,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049

出　　处：《核技术》2024年第2期93-108,共16页Nuclear Techniques

基　　金：国家重点研发计划课题(No.2019YFB1901204)资助。

摘　　要：为研究兆瓦级高效紧凑型核动力系统的运行特性,使用自主开发的热管堆瞬态分析程序TAPIRS(Transient Analysis code for heat Pipe and AMTEC power conversion space Reactor power System)和超临界二氧化碳布雷顿循环的瞬态分析程序SCTRAN/CO_(2)(Super Critical reactors Transient Analysis code/Carbon Dioxide)的耦合程序对其反应性、负荷、冷却水温度和流量等扰动进行了开环动态响应分析,并据此进行了控制系统设计。在此基础上,对线性变负荷、阶梯式变负荷以及甩负荷这三种变负荷运行工况进行了计算分析。结果表明:该核动力系统的转速对扰动的变化较为敏感,需要加以控制;低负荷下旁通会使压缩机流量上升,需对压缩机流量加以控制;系统在控制方案下能以6%FP(Full Power)·min^(−1)的速度实现0%~100%的负荷变动,且可以在任意负荷水平下运行;甩负荷下系统的波动时间变长,但是仍可达到新的稳态进行工作,且各参数处于安全范围内。本研究可为新型核动力系统的概念设计提供参考。[Background]A megawatt-class nuclear power system has been developed by coupling a heat pipe reactor with a supercritical carbon dioxide(S-CO_(2))Brayton cycle.This system offers advantages in terms of high safety,power density,and compactness.[Purpose]This study aims at the operation characteristics of this power system with high efficiency and compactness.[Methods]The coupling code of a self-developed heat pipe reactor transient analysis code,Transient Analysis code for heat Pipe and AMTEC power conversion space Reactor power System(TAPIRS),and supercritical carbon dioxide Brayton cycle transient analysis code(SCTRAN/CO_(2))were utilized to analyze the open-loop dynamic characteristics under conditions of reactivity disturbance,load disturbance,cooling water temperature disturbance,and cooling water mass flowrate disturbance.Then,the control system was designed.On this basis,three load variation operation conditions,i.e.,linear load variation,stepped load variation,and load rejection,were simulated and analyzed.[Results]The simulation results show that the rotational speed of the new nuclear power system is sensitive to the disturbances and needs to be controlled.The bypass flowrate increases under low load conditions,hence the flowrate of the compressor needs to be controlled as well.The system can adjust the load from 0%to 100%at a rate of 6%FP(full power)·min^(−1).It is capable of implementing stepped load changes,although it experiences slightly more pronounced fluctuations.Under load rejection conditions,the stabilization time might be prolonged,but it will eventually stabilize with all parameters remaining within safe limits.[Conclusions]This study provides a reference for the conceptual design of new nuclear power systems with high efficiency and compactness.

关 键 词：兆瓦级高效紧凑新型核动力系统 开环动态响应 控制系统设计 变负荷运行 

分 类 号：TL333[核科学技术—核技术及应用]