Flow analysis and flow-induced vibration evaluation for low-pressure feedwater heater of a nuclear power plant

2008 ◽  
Vol 85 (9) ◽  
pp. 616-619 ◽  
Author(s):  
Chin-Cheng Huang ◽  
Jen-Sheng Hsieh ◽  
Pay-Chung Chen ◽  
Chin-Ho Lee
2016 ◽  
Vol 821 ◽  
pp. 57-62
Author(s):  
Lukas Joch ◽  
Roman Krautschneider

The subject of this report is creation of three-dimensional thermal hydraulic model of horizontal steam generator for Dukovany nuclear power plant. A procedure is presented for simulation and analysis of secondary side of PGV-440 steam generator for nominal and increased reactor power. A two-fluid approach is applied for modeling physical processes inside the steam generator. Physical models were implemented in ANSYS Fluent CFD environment using User Defined Functions (UDFs). Results from this thermal hydraulic numerical model can be used for various other subsequent nuclear power plant operations and safety analysis.


Author(s):  
Yifeng Hu ◽  
Gang Chen ◽  
Ming Kang

High reliability and long life endurance are very important factors in the operation of large steam turbines for nuclear power plant (NPP). The low cycle fatigue (LCF) is necessary take into account problem in the design of turbine component. Thus the calculation method and assessment criterion of LCF are important for the design and development of the low pressure (LP) inner-casing. The main activity of this study was focus on the research of the low cycle fatigue in 26m2 LP inner-casing of steam turbines for NPP, which is manufactured by Shanghai Electric Power Generation Equipment Co., Ltd: STP. And detailed calculation method and assessment criterion combined with FEA analysis, fatigue curve and linear cumulative damage theory are developed to judge the life of the LP inner-casing, The approach is applied in the process of the design work of large steam turbine inner-casing.


Author(s):  
Komandur S. Sunder Raj

In recent years, the nuclear power industry has witnessed profound changes in terms of renewal of operating licenses and power uprates. Renewal of operating licenses for an additional 20 years beyond the original licensed period of 40 years entails several considerations relating to aging management, performance, reliability, availability, and maintainability. Power uprates range from a low of up to 2% due to improved techniques in feedwater flow measurement to a high of up to 20% for extended power uprates. Since the limitations of power uprates are generally encountered in design of the turbine cycle, the impact upon the performance, reliability, availability and maintainability of the equipment and components in the turbine cycle may vary from low or moderate to significant. Several nuclear power plant owners have already replaced the low-pressure turbine rotors of their nuclear units with improved designs to mitigate blade failures and forced outages due to stress corrosion cracking, to reduce inspection intervals and maintenance, achieve higher output due to improved efficiency, etc. Others are either embarking upon or planning similar initiatives to confront aging, performance, availability, reliability and maintainability concerns stemming from renewal of operating licenses as well as the need to accommodate higher pressures and flows accompanying the proposed power uprates. Typically, the original low-pressure turbine designs utilizing built-up rotors with shrunk-on disks are being replaced with monoblock rotors with fully integral disks, couplings, blading and shrouds. The last stage blading is also longer resulting in a larger annulus area. Since these replacement programs involve significant expenditures, several factors need to be considered in order to ensure that the objectives of the rotor replacement programs are met. Using a case study, this paper examines the various considerations involved in replacing the low-pressure turbine rotors for a nuclear power plant. Design, performance and test considerations that need to be addressed before and after the low-pressure turbine rotors are replaced are discussed. The use of performance modeling tools in evaluating performance gains from low-pressure turbine rotor replacements is reviewed. Finally, the paper provides recommendations for ensuring that the objectives of a low-pressure turbine rotor replacement program are met.


2021 ◽  
Vol 1985 (1) ◽  
pp. 012027
Author(s):  
Junfeng Liu ◽  
Xudong Chen ◽  
Chuangao Han ◽  
Xiaolong Ma ◽  
Fangjie Wu

Author(s):  
Eric Svensson ◽  
Dominic Marra ◽  
Michael Catapano

In 2014, the Turkey Point Nuclear Power Plant experienced a hole and a steam leak through the shell of the Unit 4, #3B Low Pressure (LP) Feedwater Heater (FWH) near the drains outlet nozzle. Although the location of the hole in the shell was below the centerline of the heater in the Drain Cooler (DC) Zone, a video probe inspection through the drains outlet nozzle revealed that the cause of the leak was actually a hole through the DC top plate, which then allowed the steam to penetrate into the DC zone and erode the shell. The shell was able to be repaired in 2014, however there was not enough time to try to fix the hole in the top plate at that time. During a planned refueling outage in 2017, an access window was cut into the shell and the DC boundary repaired using a custom fit plate to cover the hole and prevent further leakage of steam into the DC zone. The unusual configuration of the DC sealing plates in that area made the repair challenging, but overall the repair was successful and the FWH was able to be returned to service. Additionally, during the maintenance outage, two leaking tubes were discovered on the periphery of the bundle near one of the Steam Inlet Nozzles. In order to determine the source of the tube failure, a video probe inspection of the shell side of the heater was conducted. It was determined that Foreign Material (FM) was the cause of the failures. By removing the steam inlet piping elbow, the Foreign Material was able to be retrieved and removed from the heater.


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