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1.华北电力大学 核科学与工程学院 北京 102206
2.华北电力大学 核热工安全与标准化研究所 北京 102206
3.非能动核能安全技术北京市重点实验室 北京 102206
4.核反应堆系统设计技术国家级重点实验室 成都 610041
Received:08 October 2016,
Revised:16 November 2016,
Published:10 March 2017
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Jie CHEN, Tao ZHOU, Liang LIU, et al. Study on mass flow distribution of CSR1000[J]. Nuclear techniques, 2017, 40(3): 030605
Jie CHEN, Tao ZHOU, Liang LIU, et al. Study on mass flow distribution of CSR1000[J]. Nuclear techniques, 2017, 40(3): 030605 DOI: 10.11889/j.0253-3219.2017.hjs.40.030605.
以中国百万千瓦级超临界水冷堆(CSR1000)堆芯为研究对象,建立热工水力计算模型,计算出冷却剂和慢化剂温度分布、堆芯功率分布、燃料组件出口压力及流量分配等参数。计算结果表明,适当增加堆芯内部燃料组件流量比例,可以有利于径向功率展平,内外燃料组件通道出口压降,呈现"N"型变化,增大内部燃料组件的堆芯入口功率,内部组件内的流量分配也将减少,而外部燃料组件通道中的流量将增加,适当调整堆芯入口流量初始分配比例,可以使各通道功率分布展平。
Background
2
Reactor core of supercritical water-cooled reactor of China (CSR1000) is selected as research object.
Purpose
2
The establishment of thermal-hydraulic calculation model is to calculate coolant outlet flow and the outlet pressure
which is on the condition of changing the core power
flow and temperature distribution
and the size of the core inlet structure.
Methods
2
Taking the SCAC (Steady supercritical water-cooled reactor analysis code) safety analysis code as calculation method.
Results
2
The calculated results show that adjusting moderately the flow distribution of initial inlet fuel assembly will distribute uniformly the flow distribution of respective sub-channel. Inside and outside of the fuel assembly channel outlet pressure drop show an "N" shaped variation. Increasing the inlet core power of internal fuel assembly will reduce the flow distribution within internal fuel assembly.
Conclusion
2
Adjusting moderately the flow distribution of initial inlet core will distribute uniformly the power distribution.
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