摘要
在快堆蒸汽发生器中,由于运行条件和腐蚀等原因常导致传热管泄漏。高压水/水蒸气向钠侧喷射,剧烈的钠水反应可能会对蒸汽发生器造成严重破坏。为了能够更准确地预测、核算发生小泄漏时钠水反应事故对邻管(靶管)的影响,设计小泄漏钠水反应靶管损耗试验系统,对泄漏率测量、水系统控制与注射等关键技术进行了详细阐述,并与韩国、印度等钠水反应装置进行对比分析,表明:针型阀启停和高精度注射泵相结合的方式保证了测量的准确性;针型阀与气体定压相结合的方法可灵活控制注水启停及反应的发生。同时,系统设置了氩气加压系统,对系统的安全性提供了双重保障。
In the steam generator of fast reactor power plant,it is difficult to avoid the leakage of heat transfer tube due to the operation conditions and corrosion.When high pressure water/steam is injected to the sodium side,severe exothermic reaction of sodium water may cause serious damage to the heat transfer tube of steam generator.In order to more accurately predict and account for the impact of sodium water reaction accident on adjacent pipes(arget pipe)in case of small leakage,the loss test system and working condition of sodium water reaction target pipe with small leakage are designed,and the key technologies such as water leakage rate measurement,water system control and injection are described in detail.The test system is compared with South Korea,India and other sodium water reaction devices,and the results show that:in this test system,the leakage is controlled and measured by the combination of needle valve and high-precision injection pump to ensure the accuracy of measurement;the combination of needle valve and gas constant pressure can flexibly control the start and stop of water injection and the occurrence of reaction.At the same time,the system is equipped with argon pressure system,which provides double guarantee for the safety of the system.
作者
吕明宇
梁胜莹
王冲
LYV Mingyu;LIANG Shengying;WANG Chong(China Institute of Atomic Energy,Beijing 102413,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2021年第3期452-459,共8页
Nuclear Science and Engineering
关键词
快堆
蒸汽发生器
钠水反应
泄漏率
针型阀
Fast reactor
Steam generator
Sodium water reaction
Leakage rate
Needle valve