小型堆稳压器波动管双端破口试验研究

黄志刚; 张妍; 彭传新; 昝元锋; 卓文彬; 闫晓

doi:10.13832/j.jnpe.2021.06.0082

小型堆稳压器波动管双端破口试验研究

doi: 10.13832/j.jnpe.2021.06.0082

中国核动力研究设计院中核核反应堆热工水力技术重点实验室，成都，610213

详细信息

作者简介:
黄志刚（1986—），男，副研究员，主要从事反应堆热工水力研究，E-mail: huangzhigang583@163.com

中图分类号: TK124
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- 文章访问数: 265
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- PDF下载量: 30
- 被引次数: 0
出版历程
- 收稿日期: 2020-10-30
- 修回日期: 2021-04-30
- 刊出日期: 2021-12-09

Experimental Study on Pressurizer Surge Line Double-Ended Break of Small Reactor

CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 开展了模块化小堆稳压器波动管双端破口试验研究，获得了非能动安全系统的事故响应特性和一回路系统参数变化。试验研究结果表明，在稳压器波动管双端破口极端工况条件下，中压安注箱能在短时间内提供较大的稳定安注流量，及时补充系统水装量；高压安注系统运行过程比较复杂，安注流量与堆芯补水箱压力平衡管线内介质状态和中压安注系统运行状态密切相关，在1.7 h内呈间歇注入运行状态。在整个事故过程中，堆芯一直处于淹没状态，模块化小堆非能动安全系统能够确保稳压器波动管在双端破口极端工况条件下的堆芯安全。
- 小型堆 /
- 波动管 /
- 双端破口 /
- 非能动安注
Abstract: Accident response characteristics of the passive safety system and the parameter variation of the primary loop system were obtained through the experimental study of double-ended break of modular small reactor pressurizer surge line . The results show that under the extreme condition of double-ended break of the pressurizer surge line, the MP accumulator can provide a large stable safety injection flow in a short time to replenish the water capacity of the system in time; The operation process of the HP safety injection system is relatively complex, and the safety injection flow rate is closely related to the medium state of the pressure balance pipeline of the core makeup tank and the operation state of the MP safety injection system, and it is in the state of intermittent injection within 1.7 hours. During the whole accident process, the core has been submerged. The modular small reactor passive safety system can ensure the core safety under the extreme condition of double-ended break of pressurizer surge line.
- Small reactor /
- Surge line /
- Double-Ended break /
- Passive safety injection

HTML全文

图 1 试验回路流程图

Figure 1. Flow Chart of Experimental Loop

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图 2 一回路压力

Figure 2. Pressure of Primary Loop

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图 3 堆芯进出口温度

Figure 3. Core Inlet/Outlet Temperature

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图 4 RPV液位

Figure 4. Water Level of RPV

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图 5 中压安注流量

Figure 5. MP Safety Injection Flow

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图 6 ACC水位

Figure 6. Water Level of ACC

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图 7 CMT安注流量

Figure 7. Safety Injection Flow of CMT

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图 8 CMT水位

Figure 8. Water Level of CMT

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图 9 CMT进出口温度

Figure 9. CMT Inlet/Outlet Temperature

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参考文献(6)

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[4]	彭传新,鲁晓东,张妍,等. 波动管小破口失水事故实验研究[J]. 核动力工程,2016, 37(5): 63-67.
[5]	黄志刚,彭传新,张妍,等. 安注管道不同破口尺寸条件下非能动安注系统运行特性试验研究[J]. 核动力工程,2017, 38(4): 70-75.
[6]	彭传新,张妍,黄志刚,等. DVI管小破口失水事故实验研究[J]. 原子能科学技术,2016, 50(10): 1787-1792. doi: 10.7538/yzk.2016.50.10.1787