摘要
大量现有研究表明,使用合适的表面改性方法能够强化沸腾换热效果,使其在压水堆内有着广阔的潜在应用前景。但对于堆内高温高压碱性环境,这种强化换热效果能否长时间维持却鲜有研究。使用激光加工的方式,在不锈钢板状试样表面分别加工微槽、微孔、微柱三种微结构,将试样置于模拟实际堆内工况的高温高压反应釜中开展长达200 d的腐蚀实验,并对腐蚀前后试样进行池式沸腾实验与可视化研究。结果表明:三种微结构试样表面临界热流密度(Critical Heat Flux,CHF)均随腐蚀时间的增加先升高后降低,其中微孔试样在核态沸腾起始有着最大的气泡生成速率,微槽试样有着最高的CHF。
[Background]Many existing studies have shown that the use of suitable surface modification methods can enhance the boiling heat transfer effect of metal components,making it have a broad potential application prospect in the pressurized water reactor.However,for the weak alkaline environment of high temperature and high pressure in the reactor,little literature is reported on whether this enhanced effect can be maintained for a long time.[Purpose]This study aims to explore the effect of corrosion on boiling heat transfer characteristics of metal specimens with micro-structure surface.[Methods]First of all,three micro-structures of micro-groove,micro-porous and micro-columns were processed on the surface of stainless steel plate specimens by laser processing.Then the specimens were placed in the high-temperature and high-pressure environment simulating the actual reactor conditions to carry out corrosion experiments for up to 200 d.Finally,the pool boiling experiment and visualization study of the specimens before and after corrosion were carried out for comparison.[Results]The results show that the surface critical heat flux(CHF)of the three micro-structured metal specimens increases and then decreases with the increase of corrosion time,among which the micro-pores specimens have the largest bubble generation rate at the beginning of nuclear boiling,and the micro-groove specimens have the highest CHF.[Conclusions]The influence law and mechanism of long-term corrosion in pressurized water reactor on the enhanced heat transfer effect of different micro-structure surfaces are partially revealed by this study.
作者
欧阳琨
许巍
刘晓晶
何晓强
OUYANG Kun;XU Wei;LIU Xiaojing;HE Xiaoqiang(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《核技术》
CAS
CSCD
北大核心
2023年第6期145-150,共6页
Nuclear Techniques
基金
核反应堆系统设计技术重点实验室
国家自然科学基金青年基金(No.12005133)资助。
关键词
腐蚀
表面改性
沸腾换热
微结构
可视化
Corrosion
Surface modification
Boiling heat exchange
Micro-structure
Visualization
