蒸汽发生器全尺寸汽水分离装置模型开发

汽水分离装置是核动力系统蒸汽发生器(SG)重要组成部分。目前针对汽水分离装置的研究包含试验与模拟两种方法,受限于成本和计算资源,现有研究主要是对汽水分离装置中单一旋叶式分离器或波形板干燥器开展。但在SG不同位置处分离器或干燥器入口参数不相同,存在负荷不均问题。为此,本研究基于已有分离器和干燥器分离效率计算模型,对汽水分离装置适当简化,开发SG全尺寸汽水分离装置模型。研究SG中不同位置处分离器和干燥器分离效率分布特性以及干燥器液滴负荷不均情况。计算结果可为SG汽水分离装置设计提供参考,开发的汽水分离模型已植入自主化SG全流域热工水力计算分析程序STAF。     

CAP1400蒸汽发生器汽水分离装置研究

汽水分离装置是蒸汽发生器中的主要部件,其性能不仅会影响蒸汽发生器水力循环特性及水位适用性,决定上部尺寸大小,而且会影响汽轮机的正常运行。对CAP1400核电厂蒸汽发生器汽水分离装置进行了不同蒸汽负荷、饱和水量及高水位和正常水位等试验工况下的热态性能试验,获得了SP3型初级分离器与P3X型干燥器组合随蒸汽负荷、饱和水量、水位变化的分离特性。通过初级分离器和干燥器的阻力测量,分别获得了分离器和干燥器的阻力特性,对CAP1400蒸汽发生器的设计研发起到支撑作用。     

西德蒸汽发生器的汽水分离器

一、研究概况西德 KWU 为研究 U 型管蒸汽发生器两相流分离系统的特性进行了专门的试验,并根据试验结果分析了不同水位、不同汽水流量以及压力变化对分离器的压降、蒸汽湿度和疏水含汽量的影响。分离器和干燥器的综合性能与至今获得的运行经验表明,其分离系统完全能保证蒸汽发生器出口蒸汽湿度低于0.25%的规定值。目前裝设在 KWU 标准蒸汽发生器内的分离系统是大量试验的结果。研制汽水分离器之初,KWU 即确立了两个目标:①研制的分离系统必须保证在各种运行工况下     

压水堆蒸汽发生器水滴重力分离的理论研究

压水堆蒸汽发生器水滴重力分离空间是汽水分离装置的重要组成部分,是连接汽水分离器和蒸汽干燥器的纽带。蒸汽发生器的设计,除了要选用分离效率高,结构紧凑的汽水分离器和干燥器外,还要合理选择重力分离空间高度。高度太低,湿分得不到充分的重力分离,将会影响干燥效果;高度太高,将会增加蒸汽发生器和核岛设施的投资。文中对重     

蒸汽发生器汽水分离器负荷不均匀性分析

应用三维稳态热工水力软件GENEPI,对CPR1000蒸汽发生器管束区及汽水分离器区域进行热工水力分析,得到了管束区和汽水分离器入口的热工水力参数分布。结果表明,汽水分离器区域的负荷不均匀性明显,中间及热侧的汽水分离器承受的负荷较高,分析数据为汽水分离器及干燥器湿度分析提供输入数据和设计依据。对比了不同汽水分离器局部阻力系数下的结果,表明汽水分离器局部阻力系数对其负荷不均匀性有一定的影响,系数越大,流量越均匀。     

蒸汽发生器一级汽水分离器内流场数值模拟

以压水堆核电厂蒸汽发生器一级汽水分离器为研究对象，采用基于计算流体动力学（CFD）的计算软件ANSYS Fluent对湿蒸汽进入汽水分离器后的流场特性和汽水分离性能进行模拟，在模拟过程中采用了欧拉多相流模型和k-ε Realizable湍流模型相结合的计算模型。对工质流经汽水分离器的模拟结果表明，在汽相与液相经由汽水分离器流至各自出口时，出现明显的分层现象。对比不同切向出口和不同液滴粒径下的模拟结果表明，出口面积越大，汽水分离器对液滴的分离效果越好；在0.01~0.10 mm的粒径范围内，液滴粒径越大，分离效果越好。对不同负荷条件下汽水分离器分离效率的模拟结果表明，分离效率随机组负荷升高略有降低。      

下个世纪的核反应堆发展趋势

目前,世界上有6种类型的商用发电堆,但在国际核工业界只有美国首先发展的压水堆(PWR)占主导地位。世界上20个国家拥有运行中的压水堆,它们的发电量占世界总核发电量的60％。 压水堆使用普通水作为冷却剂和慢化剂。在压水堆中”,热水在高压下(防止沸腾)被泵送到蒸汽发生器,并在汽水分离回路中产生蒸汽。这一点正是压水堆与沸水堆不同之点。在沸水堆中,允     

汽水分离再热器的传热系数及出口温度随功率变化规律的分析

本文从传热学的基本原理出发,推导出核电站汽水分离再热器的传热系数随功率变化的关系式,并用该关系式导出了汽水分离再热器的出口参数随功率的变化,从而为计算和设计汽水分离再热器的温度控制系统提供了理论基础。     

汽水分离再热器多目标优化研究

汽水分离再热器在核电系统中属于大型设备,其重量、体积较大。同时,汽水分离再热器对核电系统整体热经济性具有较大影响,因此汽水分离再热器也是核电系统中的重要设备。众所周知,为了降低核电的初投资成本,提高核电系统在电力市场中的竞争力,有必要对核电系统中的大型设备进行优化设计研究。寻找可使汽水分离再热器重量、体积得以降低的设计方案。本文根据汽水分离再热器的物理过程,建立了可靠的数学模型,并利用C#语言编写了相应的评价程序。结合优化程序模块,实现了对汽水分离再热器运行及结构参数的多目标优化实例研究,其优化目标是在保证功能性的前提下,降低汽水分离再热器的重量、减小其体积。优化结果给出了汽水分离再热器多目标最优决策方案,方案显示,在满足所给定的结构及性能约束的条件下,经优化,汽水分离再热器的净重量减轻约3.4%,体积减小约4.9%,优化效果显著。通过对汽水分离再热器进行参数分析,一方面定性验证了设备模型的正确性和可用性,另一方面对于最优决策方案的合理性在一定程度上也给出了依据。结果可为核动力装置小型化优化研究提供理论参考和优化方向。     

开发有创新意义的VK—300简化沸水堆的前景

【美国《核电厂》2001年9～10月刊报道】 目前,动力工程研究开发院(RDIPE)基本完成了有创新意义的简化沸水堆VK-300的详细设计。装备有VK-300型堆设施的核电厂可用于中、小规模动力系统以及热电联供。 VK-300型堆的设计基础是较完善的核技术、成熟的大部件、VK-50原型堆在俄罗斯季米特洛夫格勒的运行经验,以及诸如SBWR(GE)和SWR(Siemens)等反应堆的设计经验。因而,VK-300采用了为WWER-1000型堆设施开发的反应堆压力容器、燃料元件和汽水分离器。 反应堆自然循环和汽-水分离的最初方案 VK-300的设计主要在开发一个自然循环回路…     

超临界水冷堆述评

超临界水冷堆(SCWR)是在高于水的临界点（374℃，22.1MPa）的温度和压力下运行的反应堆。相对于传统的轻水堆，它的热效率显著提高，可达45％。由于冷却剂在超临界状态下不发生相变，可直接与能量转换设备相联，从而简化了反应堆的结构。在SCWR中不需再循环和射流泵、稳压器、蒸汽发生器、汽水分离器和干燥器。它的主要特点是经济性好。     

PbBi-cooled direct contact boiling water small reactor

A design concept of PbBi cooled direct contact boiling water small fast reactor (PBWFR) has been formulated with some design parameters identified. Water is injected into hot PbBi above the core, and direct contact boiling takes place in chimneys. Boiling bubbles rise due to buoyancy effects, which works as a lift pump for PbBi circulation. The generated steam passes through separators and dryers for the removal of PbBi droplets, and then flows into turbines for the generation of electricity. The system pressure of 7 MPa is as the same as that of the conventional boiling water reactors (BWRs). The outlet steam is superheated by 10°C to avoid the accumulation of condensate on a PbBi free surface in the reactor vessel. The control rods are inserted from above, which is different from the original concept. This insertion was chosen since the seal of steam at the top of the reactor vessel is technically much easier than the seal of PbBi at the bottom of the reactor vessel. The electric power of 150 MWe may be the maximum which is practically possible as a small reactor with economic competitiveness to conventional LWRs. A two-region core is designed. A decrease in reactivity was estimated to be 1.5%dk/kk′ for 15 years. A fuel assembly has 271 fuel rods with 12.0 mm in diameter and 15.9 mm in pitch in a hexagonal wrapper tube. The design limit of cladding temperature is specified to be 650°C for compatibility of cladding material with PbBi. As a result, the PbBi core outlet temperature becomes 460°C. The PbBi temperature rise in the core is 150°C. The conditions of the secondary coolant steam are as the same as those of conventional BWRs with thermal efficiency of 33%. The core is designed to have the breeding ratio of 1.1 and the refueling interval of 15 years as a reactor with a long-life core. Direct heat exchangers (DHX), reactor vessel air cooling systems (RVACS) and guard vessel are designed.     

Thermo-hydraulics during start-up in natural circulation boiling water reactors

The transient behavior of natural circulation for boiling two-phase flow was investigated by simulating normal and abnormal start-up conditions to research the feasibility of natural circulation BWRs such as the SBWR. It was found that the instabilities, which are out-of-phase geysering, in-phase natural circulation oscillation and out-of-phase density wave instability, may occur during the start-up when the vapor generation rate is insufficient. In this paper, the mechanism of in-phase natural circulation oscillation induced by hydrostatic head fluctuation in steam separators, which has never been understood well enough, is experimentally clarified. Next, the effect of system pressure on the occurrences of the geysering and the natural circulation oscillation are investigated. Finally, from the results, a recommendation is provided to establish the rational start-up procedure and reactor configuration for natural circulation BWRs.     

一体化核供热堆Ⅱ型的开发及应用前景初步分析

在NHR-200的基础上,清华大学核能与新能源技术研究院开发了一体化核供热堆Ⅱ型(NHR/Ⅱ-200).本文主要阐述NHR/Ⅱ-200的一体化技术、自稳压原理、全功率自然循环冷却、非能动安全系统等一体化核供热堆的主要技术特征及核供热堆的安全特性.NHR/Ⅱ-200通过适度提高一体化核供热堆的参数,在三回路提供1.5 MPa蒸汽.NHR/Ⅱ-200不仅可应用于区域供热、热法海水淡化,还可提供工业蒸汽,并与膜法海水淡化相耦合进行海水淡化.     

蒸汽发生器干燥器CFD模拟分析

为了研究蒸汽发生器干燥器的负荷分布特性,采用计算流体动力学(CFD)软件ANSYS CFX12.1,对CPR1000蒸汽发生器干燥器进行单相流场分析,得到其流场分布,对干燥器的负荷不均匀性及分离性能进行了评估分析。此外,通过与无均汽网模型的计算结果进行对比,分析均汽网对于干燥器负荷分布及分离性能的重要性,并提出了均汽网设计的改进方法。     

Senhor-II — A computer code for loss-of-coolant accidents of pressure tube type reactors

An ATR LOCA analysis code, SENHOR-II, was developed which evaluates the loss-of-coolant accident in a reactor primary loop composed of parallel pressure tubes and downcomers connecting a steam drum to a lower header. The reactor system is divided into reservoirs and channels. The reservoirs are assumed to be saturated and equilibrated. The channels are treated one-dimensionally and their flows are assumed quasi-steady. The reservoir effect of piping, the heating up of fuel rods, the thermal capacity of structures, and the effects of steam separators and water level in the steam drum are considered. Calculated results are compared with the experimental results of the blowdown test performed with the mock-up test loop in -arai Engineering Center of PNC, and the adequacy of the calculation model and formulae is confirmed.     

新型高效汽液分离干燥器装置波纹板的制造

文章介绍了经大量试验研究,研制成功的新型高效汽液分离干燥器波纹板的制造。该研究成果已应用于国内现有核电蒸汽发生器干燥器,能满足设计和使用要求,该装置的成功研制除了适用核电领域,也可应用于火电系统及需要干蒸汽的化工及其他工业领域。     

Study on Pb-Bi-water direct contact boiling two-phase flow and heat transfer

For the development of 45w%Pb-55w%Bi cooled direct contact boiling water small fast reactor (PBWFR), Pb-Bi-water direct contact boiling two-phase flow loop has been fabricated and operated. The loop consists of a Pb-Bi flow loop (four heater pin bundle, a chimney, an upper plenum, a level meter tank, an air-water cooler, and an electromagnetic flow meter) and a water-steam flow loop (a pump, a preheated, an injection nozzle, the chimney, the upper plenum with mist separators and dryers, a condenser, a buffer tank, and an air-water cooler). At the rated operating condition system pressure is 7 MPa. The sub-cooled water was injected into a Pb-Bi flow in the chimney. A power of the heater pin bundle was controlled to obtain the inlet and outlet temperatures of the heater bundle. The Pb-Bi and steam flows were simulated analytically using one-dimensional models of frictional and form losses and a drag force. The Pb-Bi-steam two-phase frictional pressure loss was calculated by means of the two-phase flow multiplication factor of Lockhart-Martinelli model. It was found that Pb-Bi temperature decreased quickly in the chimney due to high heat transfer rate of Pb-Bi-water direct contact boiling. The volumetric overall heat transfer coefficient was 60–310 kW/m³K, and decreased with the superheat.     

螺旋管蒸汽发生器流体弹性不稳定性简化分析

利用平面圆环模拟螺旋管结构，采用平面圆环动态固有特性解析结果，结合流体力概念，提出一种螺旋管蒸汽发生器失稳临界流速的简化解析分析方法。采用该方法对２０ＭＷ模型堆和２００ＭＷ模型堆进行了流体弹性不稳定性分析，并与采用直管流弹不稳公式的计算结果进行了比较。试验结果验证了本文方法的可靠性。     

Steam drum level dynamics in a multiple loop natural circulation system of a pressure-tube type boiling water reactor

Advanced Heavy Water Reactor (AHWR) is a pressure tube type boiling water reactor employing natural circulation as the mode of heat removal under all the operating conditions. Main heat transport system (MHTS) of AHWR is essentially a multi-loop natural circulation system with all the loops connected to each other. Each loop of MHTS has a steam drum that provides for gravity based steam–water separation. Steam drum level is a very critical parameter especially in multi-loop natural circulation systems as large departures from the set point may lead to ineffective separation of steam–water or may affect the driving head. However, such a system is susceptible to steam drum level anomalies under postulated asymmetrical operating conditions among the different quadrants of the core like feedwater flow distribution anomaly among the steam drums or power anomaly among the core quadrants. Analyses were carried out to probe such scenarios and unravel the underlying dynamics of steam drum level using system code RELAP5/Mod3.2. In addition, a scheme to obviate such problem in a passive manner without dependence on level controller was examined. It was concluded that steam drums need to be connected in the liquid as well as steam space to make the system tolerant to asymmetrical operating conditions.