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以计算流体力学(CFD)为基础,编写HP-STMCs空间堆堆芯功率瞬变模型和反应性反馈模型的用户自定义函数(UDF),开发堆芯瞬态分析程序SNPS-FTASR。对程序的正确性进行验证并得到满意的结果后,用SNPS-FTASR分析1个控制鼓误动作向堆芯引入正反应性和堆芯1根热管失效时的瞬态响应特性。结果显示:在1个控制鼓误动作引入正反应性时,堆芯功率先迅速升高后因堆芯反应性负反馈而缓慢上升,最终堆芯功率稳定在额定功率的121.3%。在堆芯1根热管失效时,堆芯UN燃料芯块的温度先迅速升高后因反应性负反馈使得堆芯功率迅速下降,最终堆芯功率稳定在额定功率的88.7%,堆芯最高温度较稳定状态上升约140 K,表明热管冷却空间堆在一个控制鼓误动作和1根热管失效时热工方面是安全的。
Based on Computational Fluid Dynamics (CFD), a user-defined function (UDF) for HP-STMCs space reactor core power transient model and reactive feedback model was developed to develop the core transient analysis program SNPS-FTASR. After verifying the correctness of the program and obtaining satisfactory results, the SNPS-FTASR was used to analyze the transient response characteristics of one control drum misoperation introducing positive reactivity to the core and one heat pipe failure of the core. The results show that when one control drum misoperation introduces positive reactivity, the core power first increases rapidly and then slowly rises due to core reactive negative feedback, finally the core power stabilizes at 121.3% of rated power. When one heat pipe in the core fails, the temperature of the core UN fuel cell firstly increases rapidly and then the core power drops rapidly due to the reactive negative feedback. The final core power stabilizes at 88.7% of the rated power, the maximum core temperature This is about 140 K higher than the steady state, indicating that the heat pipe cooling space is thermally safe in the event of a control drum malfunction and a heat pipe failure.