Calculation Method of Passive Residual Heat Removal Heat Exchanger and Numerical Simulation

The tube inside and outside heat transfer mechanism of Passive Residual Heat Removal Heat Exchanger (PRHR HX) was analyzed. The calculation method of this special heat exchanger under natural convection condition in In-containment Refueling Water Storage Tank (IRWST) was carried out. The single-tube coupling model three-dimensional natural circulation in the IRWST was simulated numerically using Fluent. The heat transfer and flow characteristics of the fluid in IRWST were obtained. The comparison of the results between theoretical arithmetic and numerical simulation showed that the theoretical calculation method is suitable for the heat transfer calculation of PRHR HX.

Application of grey model on analyzing the passive natural circulation residual heat removal system of HTR-10

Using the grey correlation analysis,it can be concluded that the reactor pressure vessel wall temperature has the strongest effect on the passive residual heat removal system in HTR (High Temperature gas-cooled Reactor), the chimney height takes the second place,and the influence of inlet air temperature of the chimney is the least.This conclusion is the same as that analyzed by the traditional method.According to the grey model theory,the GM(1,1) and GM(1,3) model are built based on the inlet air temperature of chimney,pressure vessel temperature and the chimney height.Then the effect of three factors on the heat removal power is studied in this paper.The model plays an important role on data prediction,and is a new method for studying the heat removal power.The method can provide a new theoretical analysis to the passive residual heat removal system of HTR.

The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR

The technology of passive safety is the current trend among safety systems in nuclear power plant. Pas- sive residual heat removal system (PRHRS), a major part of passive safety systems of Chinese advanced PWR, is a novel design with three-fold natural circulation. On the basis of reasonable physics and mathematics models, MI- TAP-PRHRS code was developed to analyze steady and transient characteristics of the PRHRS. The calculation and analysis show that the code simulates steady characteristics of the PRHRS very well, and it is able to simulate tran- sient characteristics of all startup modes of the PRHRS. However, the quantitative description is poor during the ini- tial stages of the transition process when water hammer occurs.

Survey of experiments and code development for the passive residual heat removal system of PWR in China

Three different kinds of experiments and their typical results are surveyed for the passive residual heat removal system (PRHRS) of PWR performed in Nuclear Power Institute of China (NPIC) recent ten years. The typi- cal results of MISAP, a special code for PWR passive residual heat removal system developed and assessed by NPIC, are also described briefly in this paper.

Steady characteristic investigation on passive residual heat removal system of Chinese advanced PWR

Thermal-hydraulic characteristic investigation on passive residual heat removal system (PRHRS) of Chinese advanced PWR was conducted to provide input data for PRHRS design and to demonstrate the feasibility of unique design features. A total of 237 sets of test data at steady state have been obtained and the main influence factors on the two-phase natural circulation flow rate and residual heat removal capability were identified. On the basis of theory analysis, a correlation of two-phase natural circulation was obtained, and relative errors of 95% test data were less than ±16%. There is a considerable effect of the system status parameters on the threshold of height between heat source and heat sink, and its correlation of two-phase natural circulation system has been obtained. The steady characteristic research shows that PRHRS has the capability of removing the core decay power through natural circulation.

Current situation and development of solar heating technology in China

It is introduced the current situation and development for solar heating technology including passive solar heating and solar heating combisystems in China in this paper. Combined with the engineering application projects, the author gave the technical and economic analysis of the passive solar and solar heating combisystems in China and summarized the developing obstacle and the spreading tactics for raising marketing of the solar heating in China.

Experimental study of primary and secondary side coupling natural convection heat transfer characteristics of the passive residual heat removal system in AP1000

Passive residual heat removal heat exchanger(PRHR HX),which is a newly designed equipment in the advanced reactors of AP1000 and CAP1400,plays an important role in critical accidental conditions.The primary and secondary side coupling heat transfer characteristics of the passive residual heat removal system(PRHRS)determine the capacity to remove core decay heat during the accidents.Therefore,it is necessary to investigate the heat transfer characteristics and develop applicable heat transfer formulas for optimized design.In the present paper,an overall scaled-down natural circulation loop of PRHRS in AP1000,which comprises a scaleddown in-containment refueling water storage tank(IRWST)and PRHR HX models and a simulator of the reactor core,is built to simulate the natural circulation process in residual heat removal accidents.A series of experiments are conducted to study thermal-hydraulic behaviors in both sides of the miniaturized PRHR HX which is simulated by 12 symmetric arranged C-shape tubes.For the local PRHR HX heat transfer performance,traditional natural convection correlations for both the horizontal and vertical bundles are compared with the experimental data to validate their applicability for the specific heat transfer condition.Moreover,the revised natural convection heat transfer correlations based on the present experimental data are developed for PRHR HX vertical and lower horizontal bundles.This paper provides essential references for the PRHRS operation and further optimized design.

新型分散型抗垢剂在S Zorb装置的工业应用

中国石化广州分公司S Zorb装置为有效抑制原料侧换热器E-7101A-G因高温结垢而导致的换热器传热效率下降、换热器总压差上涨过快等影响装置长周期运行问题,决定使用浙江杭化科技股份有限公司生产的新型分散型抗垢剂HK-17DC。工业应用结果表明,HK-17DC在线除垢及阻垢作用良好,且使用HK-17DC对装置运行和产品质量无不良影响。

烟气凝变过程中SO_(3)酸雾凝结长大与脱除特性模拟研究

烟气冷凝技术能够回收湿烟气中的废水和余热,同时降低SO_(3)酸雾排放量。该文通过建立烟气冷凝、颗粒运动及颗粒凝结长大模型,对烟气凝变过程中SO_(3)酸雾的凝结长大和脱除特性进行研究,分析关键影响因素,并讨论了酸雾长大和脱除机理。结果表明:SO_(3)酸雾经过凝结长大后在换热器出口粒径呈双峰分布,最高数量浓度在微米范围;亚微米粒径的酸雾捕集机理以热泳和扩散泳为主,提高入口烟气温度和相对湿度,降低壁面温度和入口烟气流速都有利于酸雾粒径的增长和脱除。微米粒径的酸雾捕集机理以惯性碰撞和拦截为主,提高烟气流速有助于微米粒径酸雾的脱除。

基于不同功率的非能动安全壳热量导出系统实验研究

“华龙一号”非能动安全壳热量导出系统(passive containment heat removal system,PCS)和“玲龙一号”非能动安全壳热量导出系统设计原理相同,但系统功能和设计准则不尽相同。为了掌握影响系统换热能力和运行的关键因素,本文结合不同项目的特点,从综合性能实验需求和实验结果等方面,研究、分析“华龙一号”非能动安全壳热量导出系统与“玲龙一号”非能动安全壳热量导出系统设计中的典型现象,发现降低冷却水箱水位可以提升系统的换热能力、改变冷管段阻力对系统的换热能力更敏感和冷管段隔离阀关闭方案在开启时可能会有一定的风险,从而提出后续优化研究和设计中需要重点关注的影响因素。文中结论可用于指导相关系统设计工作。

“华龙一号”PCS系统对氢气风险的影响研究

“华龙一号”(Hualong pressurized reactor 1000,HPR1000)设置了多种严重事故预防与缓解措施,有必要对氢气风险控制相关的缓解措施与其他缓解措施综合作用下的氢气风险进行研究。利用严重事故一体化软件建立了“华龙一号”电厂模型,结合严重事故后安全壳内氢气可燃性判断准则,研究了典型事故后非能动安全壳热量导出系统(passive containment heat removal system,PCS)作用下的安全壳内氢气浓度分布,分析了PCS对严重事故后氢气风险的影响。研究结果可为“华龙一号”严重事故管理措施的有效性论证提供支持。

池式钠冷快堆固有热工流体安全特性研究

本文提出池式钠冷快堆具有一种重要特性,即固有的热工流体安全特性,分析其形成机理,并采用实际反应堆和钠工质台架的自然循环试验数据,以及不同系统程序的预测计算,对其进行论证。结果表明,池式钠冷快堆具有固有的热工流体安全特性。在事故紧急停堆初期,池式钠冷快堆仅依靠该固有安全特性即可保证堆芯安全,后期只需要在堆内温度上升到安全限值之前建立堆外有效热阱即可。有效热阱可以是专门设置的余热排出系统也可以是堆容器常规热损失项;对于将换热器布置在热池或冷池的较典型事故余热排出系统,从其启动到对堆芯发挥冷却作用需要相对较长时间。此时段,反应堆需依赖固有的热工流体安全特性来抑制堆芯温升,保证堆芯安全。

含绕丝棒束低流速时阻力特性的实验研究

钠冷快堆含绕丝棒束组件低流速时的摩擦阻力特性,是设计钠冷快堆非能动事故余热排出系统的重要参数。使用水作为测量介质,采用改进的液柱测压方法,准确测量了一个有机玻璃材质37棒绕丝棒束组件雷诺数Re=200~1 100时的摩擦阻力特性。结果表明,被测量组件从层流向湍流转捩的临界Re为370。组件的入口段长度随着流速的增加而增大,随着流动开始向湍流转变而减小。现有的绕丝棒束摩擦阻力系数经验公式中,UCTD公式与实验值最接近:在层流区,UCTD公式高估了约7%,在层流向湍流转换区,UCTD公式计算值与实验值基本一致。同时,UCTD和CTS公式还高估了组件从层流向湍流转捩的临界Re。

液压胀接残余接触压力计算及相关参数影响分析

胀接压力适宜控制范围的确定,关键在于准确计算胀接后换热管与管板间的残余接触压力。现有残余接触压力理论计算方法忽视换热管反向屈服问题,导致残余接触压力计算值与实际不符。文中基于材料理想弹塑性和平面应变假设,给出了Mises屈服准则下胀接残余接触压力理论计算方法详细推导过程,讨论分析了换热管弹性模量、屈服强度、壁厚等变化对残余接触压力的影响,该方法可适用于先焊后胀胀接工艺下胀接残余接触压力预测。

全厂断电事故下壳内热工水力与非能动安全壳热量导出系统耦合特性实验研究

为研究全厂断电始发的严重事故下安全壳内热工水力与非能动安全壳热量导出系统的耦合特性,本文利用PANGU安全壳综合试验装置研究了全厂断电事故工况下壳内温度分布特性、氦气分布特性以及壳内流场特性,并分析了非能动安全壳热量导出系统在安全壳与非能动安全壳热量导出系统耦合的复杂热工水力环境下的工作状态。结果表明:在全厂断电事故工况下,非能动安全壳热量导出系统具有足够的排热能力,能够保证安全壳的压力峰值小于设计值,且具有足够的安全裕量。随着事故进程的发展,壳内温度分布逐渐趋于均匀。氦气受到壳内内部环流的作用以及浓度扩散的影响,其分布不均匀性在氦气停止输入后逐渐降低。

换热器管板胀接接头开槽结构的模拟与试验研究

为增强换热器管板胀接接头在常温下的抗拉强度,通过有限元分析和试验验证,开发一种具有阶梯型开槽结构的管板接头。建立不开槽、标准开槽和阶梯开槽的三种胀接接头的理论分析模型,利用弹塑性理论进行胀接过程和接头拉脱过程的有限元模拟,探究不同开槽形式的胀接接头处的拉脱破坏形式,并且对三种胀接接头开展常温下的拉脱试验,得出不同开槽形式的胀接接头的拉脱力。结果表明:开槽结构的胀接接头的拉脱力明显高于不开槽结构的胀接接头,并且阶梯槽胀接接头的拉脱力最大。阶梯槽胀接接头在拉脱过程中会出现“驼峰形”的陡坡,拉脱难度更大。胀接接头在开槽位置形成多条较宽的高应力残存环带,这些高应力残存环带是保证开槽接头密封性和抗拉脱力的关键因素。

3.9Mt/a渣油加氢装置节能优化运行分析

渣油加氢装置是炼油厂的能耗大户,其中电耗和燃料气消耗所占比例最大。上海石化渣油加氢装置采取了一系列措施降低电能和燃料气消耗,通过新氢压缩机新增HydroCOM气量无级调节系统、提高液力透平投用率、使用节能风机叶片、加热炉系统综合升级改造、提高高压换热器换热效率等措施,装置节能工作取得了较大成绩,装置能耗由2018年的17.337kg标油/t降低到2021年的11.474kg标油/t,三年来装置能耗共降低了33.82%,高能耗的状态得到很大的改善。目前装置能耗相较于同类先进装置仍存在较大的差距,还存在较大潜力,今后可以采取优化冷低分油换热流程、提高蜡油进料温度、优化分馏塔操作温度、提高机泵效率、提高净化水回用率、优化反应器温度、优化反应进料泵备泵预热方式等手段,进一步改造和节能优化,降低渣油加氢装置能耗。

脉动载荷下换热器管板接头塑性失效研究

管板接头是换热器常见失效部位,其中交替塑性失效模式缺乏研究。基于材料的多线性等向强化(MISO)本构模型,对U型管式换热器角焊缝管板接头和新型内孔焊管板接头进行了弹塑性数值模拟。通过提取管板管桥中心及管板管孔附近区域的节点的应力及应变数据,得到了在脉动递增载荷下的双向应力和应变规律。结果表明,在脉动载荷的递增加载与卸载过程中,两管板接头的残余应力与残余应变存在差异;随着脉动幅值的递增,塑性应变不断累积,为防止结构最终发生塑性失效,需对应变进行合理控制。通过分析发现管接头内缘处是较容易发生交替塑性失效的部位,在对换热器管板接头失效分析时,应重视载荷历程和焊接接头形式对管板的影响。

失水事故下安全壳内热工水力与非能动安全壳热量导出系统耦合特性

为研究冷管段失水事故下安全壳内热工水力特性、非能动安全壳热量导出系统的耦合特性与失水事故后安全壳的响应特性,本文基于相似理论建立了一套大比例安全壳综合试验装置。通过该实验装置获得压力、壳内气体温度、壳内气体成分与浓度等参数,对安全壳大空间内温度分布、不凝结气体分布以及壳内流场的特性进行研究。结果表明:在安全壳与非能动安全壳热量导出系统耦合作用下,非能动安全壳热量导出系统具有足够的排热能力,可以确保事故工况下安全壳内压力得到有效抑制,壳峰值压力均低于设计限值,且具有足够的安全裕量。同时,随着喷放进入后期,壳内温度与不凝结气体分布的不均匀性逐渐降低,壳内呈现环流状态。本文也可为后续自主开发模拟带有非能动安全壳热量导出系统的安全壳内热工水力行为的程序提供有力的支持,进而提高我国核电设计能力与技术水平。