摘要
第3代大型先进压水堆设置非能动余热排出系统,包括大容积高位水箱及其内置的非能动余热排出热交换器(PRHRHX)和自动降压系统(ADS)喷洒器,在运行过程中呈现出复杂的气液两相热工水力现象和独特的传热、传质特性。近年来随着非能动安全系统工程需求和相关研究的兴起,国内外开展了一些针对大容积非能动冷却水箱及其内置关键部件热工水力特性的相关研究,本文对上述问题的研究现状进行综述。对于PRHRHX,评价特殊C型管束在单相自然对流、两相沸腾条件下的传热特性,分析经典传热模型及改进经验关联式的适用性;对于ADS1~3级喷洒器高温高压蒸汽喷放冷凝过程,综合分析其喷放冷凝流型、特征参数、冷凝换热系数等关键传热、传质特性。以上研究大幅丰富了第3代大型先进压水堆大容积水箱的设计理论,并进行了实际工程应用。本文在此基础上,对相关研究未来发展方向进行展望。
The third generation of large advanced pressurized water reactor (PWR) is equipped with the passive residual heat removal system (PRHRS),including the large-volume high-level water tank and its built-in passive residual heat removal heat exchanger (PRHR HX),and automatic depressurization system (ADS) sparger.It has complex two-phase flow behavior and special heat and mass transfer characteristics in the operation process.In recent years,with the rise of engineering requirements and related researches on the passive safety system,some researches on the thermal-hydraulic characteristics of passive cooling water tank and its built-in key components have been carried out at home and abroad.In this paper,the review on these problems research was summarized.For the PRHR HX,the heat transfer characteristics of the special C-tube bundle under both the single-phase natural convection and two-phase boiling process were evaluated.The applicability of the classical heat transfer models and the modified empirical correlations was analyzed.In aspect of the high temperature and high pressure steam ejection and condensation of ADS 1-3 sparger,various heat and mass transfer influencing factors including spraying condensation flow patterns,condensation characteristic parameters,condensation heat transfer coefficient,etc.,were evaluated.The above researches greatly enrich the design theory of the large-volume water tank.Furthermore,future development directions of the researches on the key heat transfer characteristics of the passive cooling water tank of large advanced PWR were prospected.
作者
陆道纲
张钰浩
李向宾
周世梁
曹琼
隋丹婷
王汉
LU Daogang;ZHANG Yuhao;LI Xiangbin;ZHOU Shiliang;CAO Qiong;SUI Danting;WANG Han(School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,Beijing 102206,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2019年第10期1930-1940,共11页
Atomic Energy Science and Technology
基金
国家科技重大专项资助项目(2017ZX06004002-006-002)
关键词
内置换料水箱
非能动余热排出热交换器
第1~3级自动降压系统
传热特性
综述
in-containment refueling water storage tank
passive residual heat removal heat exchanger
automatic depressurization system stage 1-3
heat transfer characteristic
review