CSR1000堆芯流量分配的研究

陈杰; 周涛; 刘亮; 夏榜样

doi:10.11889/j.0253-3219.2017.hjs.40.030605

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CSR1000堆芯流量分配的研究

核能科学与工程 | 更新时间：2021-05-19

- CSR1000堆芯流量分配的研究
- Study on mass flow distribution of CSR1000
- 核技术 2017年40卷第3期文章编号：030605
- 作者机构：
  
  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
- 作者简介：
  
  [ "陈杰, 男, 1991年出生, 2015年毕业于南华大学, 现为硕士研究生, 研究领域为核热工水力与安全", "CHEN Jie, male, born in 1991, graduated from University of South China in 2015, master student, focusing on nuclear thermal hydraulics and safety" ]
  周涛, E-mail:zhoutao@ncepu.edu.cn ZHOU Tao, E-mail:zhoutao@ncepu.edu.cn
- 基金信息：
  
  中核核反应堆系统设计技术重点实验室课题(2014BH0041);中央高校基本科研业务专项项目(2014BJ0086)
- DOI：10.11889/j.0253-3219.2017.hjs.40.030605
  中图分类号： TL36
- 收稿日期：2016-10-08，
  
  修回日期：2016-11-16，
  
  纸质出版日期：2017-03-10
- 稿件说明：
移动端阅览
陈杰, 周涛, 刘亮, 等. CSR1000堆芯流量分配的研究[J]. 核技术, 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
陈杰, 周涛, 刘亮, 等. CSR1000堆芯流量分配的研究[J]. 核技术, 2017,40(3):030605 DOI： 10.11889/j.0253-3219.2017.hjs.40.030605.

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.

摘要

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。

Abstract

Background

Reactor core of supercritical water-cooled reactor of China (CSR1000) is selected as research object.

Purpose

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

Taking the SCAC (Steady supercritical water-cooled reactor analysis code) safety analysis code as calculation method.

Results

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

Adjusting moderately the flow distribution of initial inlet core will distribute uniformly the power distribution.

关键词

Keywords

references

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