Transient Thermohydraulic Characteristics of HP-STMCs Space Reactor Core
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摘要: 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。Abstract: The power transient model and reactivity feedback model on transient thermohydraulic characteristics analysis of Heat Pipe Segmeuted Thermoelectric Module Converters(HP-STMCs) cooled space reactorcore were built by using CFD interface UDF, and the HPSR core transient analysis code SNPS-FTASR was developed and approved with steady state calculation. The transient response of HP-STMCs core was studied on reactivity-insertion accident transient and a heat pipe failed transient. The results show that the power and UN temperature increased rapidly, then the power and temperature increased slowly to a final new steady state because of the core reactivity temperature feedback. The new power is 121.3% rated power. When a heat pipe failed, the UN fuel temperature increased rapidly and a great negative reactivity was brought to the core, thus the HP-STMCs core underwent a rapid power decrease and finally operated at 88.7% rated power. The maximum temperature of UN fuel increased by 140 K. It is approved by the result that the HP-STMCs core is safety at transient state including reactivity-insertion accident and a heat pipe failed.
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Key words:
- Heat pipe cooled space reactor /
- Reactivity /
- Transient response /
- Heat pipe failures
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