摘要
通过反应堆压力容器外部冷却(ERVC)实现熔融物堆内滞留(IVR)技术是核电厂严重事故缓解的重要措施之一。在本文的研究中,建立了二维切片式、全尺寸的试验台架FIRM,开展严重事故条件下反应堆压力容器ERVC-临界热流密度(CHF)试验研究。试验采用去离子水作为试验工质,获得了反应堆压力容器下封头ERVC过程的CHF限值。研究了真实表面材料对CHF的影响及其影响机理,讨论了在去离子水下表面材料SA508 Gr3.Cl.1钢的老化效应。本试验研究对于认识反应堆压力容器IVR-ERVC条件下的CHF行为、提高反应堆压力容器安全性有重要意义。
In-vessel retention（IVR）of molten corium through external reactor vessel cooling（ERVC）is one of the most important severe accidents management strategies.In this paper,a two dimensional full scale facility FIRM was built to investigate critical heat flux（CHF）behaviors under severe accident conditions.CHF limits of RPV lower head in the process of ERVC were investigated with deionized water as working fluid.The influence of real surface material SA508Gr3.Cl.1steel and its mechanism were investigated.The aging effect of SA508 Gr3.Cl.1 steel in deionized water was discussed.The test result will provide a profound understanding of CHF behaviors with real RPV material under IVR-ERVC condition and will be of significance to improve the safety of reactor vessel.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2016年第10期1782-1786,共5页
Atomic Energy Science and Technology
基金
国家科技重大专项资助项目(2010ZX06002-04)
