Exploration of Construction Organization for Maintenance of Steam Turbine Equipment in Thermal Power Plants

The continuous development of the power industry has had a positive impact on thermal power plants,helping them maintain a good production form.In the use of steam turbine equipment in thermal power plants,to prolong its lifespan and avoid safety hazards,it is necessary to pay attention to strengthening maintenance and construction organization,better implementing effective organizational work,and effectively applying steam turbine equipment to ensure the sustainable development of thermal power plants.This article discusses the concept of equipment maintenance from the perspective of steam turbine equipment in thermal power plants,analyzes the current situation of equipment maintenance,and proposes a specific construction organization to provide a reference for steam turbine equipment maintenance.

Performance and Economic Study of Oxy-fuel Gas Turbine Power Plant Utilizing Nuclear Steam Generator

The authors propose a new closed cycle oxy-fuel gas turbine power plant that utilizes a nuclear heat generator. A pressurized water reactor （PWR） is designed to supply saturated steam to an oxy-fuel gas turbine for a specific power output increase The saturated steam from the reactor can have lower pressure and temperature than those of an existing PWR. In this study, the authors estimated plant performances from a heat balance model based on a conceptual design of a hybrid plant and calculated the generating costs of the proposed plant from the Japanese cost data of an existing PWR plant and an liquefied natural gas （LNG） combined cycle gas turbine plant. The generating efficiency of an oxy-fuel gas turbine plant without a nuclear steam generator is estimated to be less than 35%. Based on this efficiency, with a nuclear steam generator contributing to the power output of the proposed hybrid plant, the corresponding generating efficiency is estimated to be around 45%, even if the steam conditions are lower than in an existing PWR. The generating costs are 15-20% lower than those calculated from the weighted heat performances of both an oxy-fuel gas turbine plant without a nuclear steam generator and an existing PWR plant.

Transient Analysis of Steam Generator in PWR Nuclear Power Plant

The water level control system of steam generator in a pressurized water reactor of nuchear power plant plays an important role which effects the water level control of the steam generator are due the reverse dynamics behavior,so the transient analysis of the steam generator should firstly solve their mathematical models.For determination of dynamic behavior and design and testing of the control system, a nonlinear math model is developed using one dimensional conservation equations of mass,momentum and energy of primary and secondary sides of the steam generator. The nonlinear model is verified with standard power plant data available in the references, then the steady states and transient calculations are performed for full power to 5% power reactor operation of the steam generator of Chinese Qinshan Nuclear Power Plant.

Failure Analysis on the Thrust Wear Detector of Turbine in Nuclear Power Plant

1GME037MV is the thrust wear detector of turbine.Before the turbine run up,the value of this channel often fluctuated.The engineer checked the channel,terminal,continuity,insulation,and driver and so on,no problem was found.At last,when disconnecting the end of the detector from the driver,then re-connected the end to the driver,the channel value is OK,after a while it became wrong again.Measured the resistance of the detector,it is 13O hm when the channel is OK,and 76 Ohm when the channel is wrong.According to the result of the checked,the conclusion is the character of the detector had changed.Both the measured value GME037MV and GME038MV are high 0.7mm,the turbine will trip,In the end the detector of GME037MV was replaced when the unit shut down.

Design of Steam Turbine for Electric Power Production Using Heat Energy from Palm Kernel Shell

The steam turbine is a prime mover that converts kinetic energy in steam into rotational mechanical energy through the impact or reaction of the steam against the blades. The aim of this study is to design a steam turbine for a small scale steam power plant with target of producing electricity. The turbine is driven by the heat energy from palm kernel shells as a renewable energy source obtained at a lower or no cost. The study was concentrated on design of turbine elements and its validation using computer packages. Specifically, the microturbine design was limited to design, modeling, simulation and analysis of the rotor, blades and nozzle under the palm kernel shell as fuel for the micro power plant. In blade design, stress failures, efficiency and blade angle parameters were considered. In casing volume design, the overall heat transfer and mean temperature, and different concepts were applied. The thermal distribution on stator and rotor was considered in order to determine its level of tolerance. The design software packages used for design validation were Solidworks and Comsol Multiphysics for analysis. Simulation results showed that the designed steam turbine can adequately tolerate change in stress/load, torsion/compression, temperature and speeds.

Forced Compressed Air Cooling System for a 300 MW Steam Turbine in Waigaoqiao Power Plant

The 300 MW steam turbine installed in Waigaoqiao Power Plant with combined HPIP cylinders of double casing structure is a product of the Shanghai Turbine Works utilizing licensed technology. It has a large heat storage capacity and good thermal insulation, so the metal temperature of first stage of HP cylinder (FSMTI) may reach 400-450℃ after shut down and it takes 7-8 days to cool to 150℃ by natural cooling, Now with a forced cooling system the cooling time may be reduced to 40 hours, so that the turbine may be opened for repair work in about 5-6 days. The cooling system for #2 unit and test procedure are briefly described below.

Variants of Nuclear Power Plants of Small and Medium Power with Heavy Liquid-Metal Coolants

New design solutions have been proposed for a BRS-GPG type reactor circuit, which are different from transport and stationary low and medium-powered reactor installations cooled with heavy liquid-metal coolants, and which correspond to the evolutionary development of such installations. While developing these solutions, the available experience in creating and operating Soviet pilot and commercial power plants cooled with lead-bismuth coolants was used, including investigations, primarily experimental ones, carried out by team of authors in justification of a capacity range (50 - 250 MW) of low and medium-powered reactor plants with horizontal steam generators (BRS- GPG) proposed and elaborated at the NNSTU.

基于超声TOFD技术的管道焊缝在役检查方案研究

为增强“华龙一号”核电机组主蒸汽管道焊缝在役阶段缺陷定量的准确性,利用便携式自动超声TOFD检测系统对52mm厚低合金钢产品环焊缝开展检测试验,结果表明,超声TOFD技术可以较好地适用于厚壁焊接结构的检测,具有较高的检测灵敏度。基于对超声TOFD技术近表面盲区问题的分析讨论,提出了采用超声TOFD技术与常规脉冲反射技术相结合的方案对“华龙一号”核电厂主蒸汽管道焊缝进行自动化超声检查,以满足焊缝缺陷精确定量和结构完整性评价需要。

Some Technical Solutions for Environmental Protection System during Accidents at Nuclear Power Plants

The paper reports some technical solutions, which suggested or used for increasing of environmental protection during accidents at NPPs. For NNPs with two protective shells and pressure release system such as WWER-1000 a comprehensive, passive-mode environmental protection system of decontamination of the radioactive steam-air mixture from the containment and the intercontainment area was suggested. This system includes the “wet” stage (scrubbers, etc.), the “dry” stage (sorption module), and also an ejector, which in a passive mode is capable of solving the multi-purpose task of decontamination of the air-steam mixture. For WWER-440/230 NPPs three protection levels: 1) a jet-vortex condenser;2) the spray system;3) a sorption module were suggested and installed. For modern designs of new generation NPPs, which do not provide for pressure release systems, a new passive filtering system together with the passive heat-removal system, which can be used during severe accidents in case all power supply units become unavailable, was proposed and after modernization was installed at the KudanKulam NPP (India).

Fault prediction method for nuclear power machinery based on Bayesian PPCA recurrent neural network model

Early fault warning for nuclear power machinery is conducive to timely troubleshooting and reductions in safety risks and unnecessary costs. This paper presents a novel intelligent fault prediction method, integrated probabilistic principal component analysis(PPCA), multi-resolution wavelet analysis, Bayesian inference, and RNN model for nuclear power machinery that consider data uncertainty and chaotic time series. After denoising the source data, the Bayesian PPCA method is employed for dimensional reduction to obtain a refined data group. A recurrent neural network(RNN) prediction model is constructed, and a Bayesian statistical inference approach is developed to quantitatively assess the prediction reliability of the model. By modeling and analyzing the data collected on the steam turbine and components of a nuclear power plant, the results of the goodness of fit, mean square error distribution, and Bayesian confidence indicate that the proposed RNN model can implement early warning in the fault creep period. The accuracy and reliability of the proposed model are quantitatively verified.

Investigation of the interaction of material of fuel cladding for WWER-1000 reactor with steam at a temperature of accident overheatings

The subject of this study is the oxidation of fuel rod cladding made of material Zr1Nb(0.1% O) in steam at temperatures in the range of 660℃ to 1200℃ with a surface in the initial state (after manufacturing - grinding) and after additional chemical etching. The changes in the microstructure of tubes due to the interaction with steam were investigated. A comparison was made between the oxidation rate of this material (weight gain) and the data on the oxidation of other alloys for nuclear power plants. The oxidation rate of Zr1Nb(0.1% O) is close to the oxidation rate of other zirconium alloys. It is shown that after chemical treatment of the surface of the samples there is a more even growth of oxide films, and they have a smaller thickness for the same time of exposure than after mechanical grinding. Surface treatment before oxidation also affects the change of microstructure of samples when heated to high temperatures.

16m双柱立车在核电汽轮机低压内缸研制中的必要性分析

本文根据自主型核电汽轮机低压内缸结构、尺寸、重量、精度,加工现状,以及核电汽轮机发展趋势和市场前景,提出了添制16 m双柱立车在核电汽轮机低压内缸研制中的必要性,同时拟定了机床的主要技术参数。

华龙一号核电机组的供热方案探讨

文章分析了核电机组供热特点。针对华龙一号汽轮机组进行了两种不同供热方案的设计,对比分析了两种供热方案下汽轮机机组的出力,不同负荷下供热量和供热压力的影响等,从而针对不同需求推荐相应的供热方案。

百万千瓦级核电汽轮机通流改造提效的研究与应用

由于汽轮机通流技术更新迭代及核电厂延寿、提升效率的需求,核电汽轮机在运行20~30年后需要考虑进行一次整体通流改造。某集团2003年投产的两台百万千瓦级合资型汽轮机改造前存在出力达不到设计值问题,通过研究汽轮机隔板通流面积与反应堆的匹配关系并考虑大修工期及造价因素,进行更换前、后流道第一级隔板和后流道第3级隔板的通流改造,改造后两台合资型汽轮机分别提升出力10.02MW、6.98MW。该集团1994年投产的两台百万千瓦级进口型汽轮机长期运行后暴露出铆钉头冲刷脱落、静叶摩擦阻力及扰动损失大、低压缸余速损失大的问题,在20年大修窗口进行高压缸转子、隔板等通流部件更换的通流改造,改造后两台进口型汽轮机分别提升出力8.8MW、8.6MW。

军用舰船动力装置技术应用现状及未来趋势展望

以动力装置对军用舰船的影响作为切入点,概要介绍舰船动力装置的定义及相关技术要求,并对柴油机、汽轮机、燃气轮机等几类常见动力装置的技术特点及应用现状进行重点研究,随后对相关动力装置的当前主要技术问题进行详尽阐述。最后,对上述舰船动力装置的未来发展趋势及相关技术研发策略开展重点研究。就目前而言。柴油机是中、小型舰船(涵盖各类水面舰船与潜艇)和军辅船的重点发展方向;燃料电池与斯特林发动机是常规潜艇不依赖空气的推进(AIP)系统的重点发展方向;汽轮机和燃气轮机是大、中型水面舰船动力装置的重点发展方向;核动力装置则是航空母舰与核潜艇的重点发展方向。考虑到国际局势的风云变幻,针对动力装置的设计、研发、制造与优化能进一步提升舰船的整体性能,为我国的海防事业作出不可磨灭的贡献。

汽轮机高位布置燃煤发电系统调频动态特性模拟研究

汽轮机高位布置技术可大幅缩短四大管道的长度,降低四大管道阻力,有望在降低发电煤耗率的同时提升机组的响应能力。采用GSE软件建立了660MW汽轮机高位布置超超临界燃煤发电机组动态模型,研究了主汽阀、高加抽汽节流和低加抽汽节流参与一次调频时的调节性能,并与汽轮机常规布置机组进行比较。结果表明:汽轮机高位布置可减少主汽阀参与一次调频时的调节时间,负荷扰动分别为-0.3%P e、-0.4%P e和-0.5%P e时,高位布置机组的调节时间分别减少了2s、2.1s和2.6s,负荷扰动分别为+0.3%P e、+0.4%P e和+0.5%P e时调节时间减少了2.1s、3.5s和4.1s;但是汽轮机高位布置对抽汽节流参与调频时的调节时间影响较小。

基于CFD的阀门保温层传热仿真分析

非能动二次侧余热排出(PRS)系统的蒸汽管道与主蒸汽管道相连,给水管线与PRS系统凝水管线相连。在开展系统热工流体分析时发现,若非能动二次侧余热排出系统蒸汽管线与二回路主蒸汽管线之间的蒸汽隔离阀常开,高温蒸汽直接作用于阀门,加上保温层的作用阻碍阀门散热,可能会导致蒸汽隔离阀内部温度过高,引起阀门电装无法正常动作。本文计算分析了PRS系统蒸汽隔离阀带保温层状态下的传热情况,判断阀门在高温流体下是否能保证电机的可用性。

基于遗传算法的核电站汽轮机抽汽流量优化计算

为提高核电站汽轮机系统的效率和运行性能,确保经济、稳定和可靠的电力供应,开展基于遗传算法的核电站汽轮机抽汽流量优化计算研究。利用神经网络预测核电站汽轮机抽汽流量,以核电站汽轮机抽汽流量为优化目标,各抽汽口抽汽流量和一、二级再热蒸汽流量为优化变量,采用遗传算法进行核电站汽轮机抽汽流量优化计算目标函数求解,所得最优解即为抽汽流量优化计算结果。实验结果表明,该方法的核电站汽轮机抽汽流量优化计算结果与实际值更接近,说明该方法的计算精准度高,应用效果好。

CPR1000核电厂工业供汽的反应堆和供汽回路协同控制研究

工业供汽是核能综合利用的一种主要方式,反应堆与供汽回路的协同控制是核电厂实现工业供汽的关键。本文提出了一种协同控制方案:优化反应堆控制系统(RRC)堆机接口信号的匹配程度,制定供汽回路的控制策略。通过系统程序的数值模拟与计算分析,结果表明:使用合理的反应堆控制系统堆机接口方案和供汽回路控制策略,反应堆控制系统能够应对运行瞬态,核电厂能够保持安全稳定运行。

大型核电机组对外供汽工艺方案研究与分析

基于某核电厂周边工业用汽需求和路由距离参数,结合核电厂技术特性,提出了以核电厂核能作为热源,通过蒸汽转换方式产生外供蒸汽的总体技术方案,拟定转换系统出口蒸汽的工作温度和工作压力分别为270℃、1.8MPa.a。基于总体方案,设计了两种蒸汽转换系统工艺方案(方案一和方案二),从系统配置和热力性能方面对比了两种工艺方案,结果表明,方案二系统工艺更简略,对电厂的接口影响较低,经济性略优。蒸汽转换总体方案和工艺方案可为核能供汽项目提供参考。