Design on material database of nuclear power equipment

2015 ◽  
Author(s):  
L.J. Yao ◽  
X.Y. Tong
Keyword(s):  
Nuclear Power ◽  
Power Equipment

Nuclear Power Equipment (Design)

2014 ◽  
Vol 83 (4) ◽  
pp. 270-274 ◽  
Author(s):  
Masashi KAMEYAMA
Keyword(s):  
Nuclear Power ◽  
Equipment Design ◽  
Power Equipment

A review of fretting study on nuclear power equipment

2020 ◽  
Vol 144 ◽  
pp. 106095 ◽  
Author(s):  
Zhen-bing Cai ◽  
Zheng-yang Li ◽  
Mei-gui Yin ◽  
Min-hao Zhu ◽  
Zhong-rong Zhou
Keyword(s):  
Nuclear Power ◽  
Power Equipment

NC Machining and Simulation for Large Channel Head

2011 ◽  
Vol 121-126 ◽  
pp. 2110-2115
Author(s):  
Tian Chen ◽  
Zhong Hai Yu ◽  
Di Shi Liu ◽  
Jing Wang
Keyword(s):  
Nuclear Power ◽  
Tool Path ◽  
Tool Path Generation ◽  
Simulation Software ◽  
Path Generation ◽  
Power Equipment ◽  
Software Platform ◽  
Processing Methods ◽  
Processing Scheme ◽  
Large Channel

As one of the key components of nuclear power equipment, large nuclear power head has a complicate shape, great allowance of processing and difficult to produce. There is no any successful experience for reference. In this paper, one type of nuclear power head is our research object. We mainly researched on the NC processing programming of large nuclear power head and implemented processing simulation by alternative applying variety of processing methods, including calculation and simulation of tool path, generation of pre-processing files, and development of post-processor based on specific milling processing center, and the generation of NC codes. Finally, through Vericut, the simulation software platform, simulation verification of NC codes was implemented. The results indicated that the processing scheme was reasonable, NC codes were right and there was no phenomenon of over-cutting and under-cutting happening.

Research and Application of CAD/CAE Integration for Nuclear Power Equipment Design

2019 ◽  
Author(s):  
Zhao Dong ◽  
Jing Xiaodong ◽  
Huang Shaoyong ◽  
Cheng Jianke
Keyword(s):  
Nuclear Power ◽  
Equipment Design ◽  
Power Equipment

scholarly journals PECULIARITIES OF CALCULATING THE CYCLIC STRENGTH OF IMPORTANT THREADED JOINTS

2002 ◽  
Vol 8 (1) ◽  
pp. 42-48
Author(s):  
Mindaugas Leonavičius ◽  
Algimantas Krenevičius ◽  
Stanislav Stupak ◽  
Marijonas Šukšta
Keyword(s):  
Nuclear Power ◽  
Cyclic Strength ◽  
Minimum Size ◽  
Power Equipment ◽  
Calculation Methods ◽  
Limit States ◽  
Theoretical Investigations ◽  
Asme Code ◽  
Threaded Joints ◽  
Definition Of

The calculation of the strength of important threaded joints is started by defining the minimum size of the cross-section of bolts (studs). Then the static and cyclic strength is tested. The studs of the demountable joints of nuclear power equipment are calculated in accordance with the norms of the Russian Federation and the ASME Code. The calculation methods coincide in essence, they are based on similar limit states; however, there also some differences exist. The authors investigate and compare both methods in their work. There is a brief analysis of calculation methods in the article. For closer definition of standards and their substantiation the authors used experimental and theoretical investigations performed at Laboratory of Strength Mechanics of Vilnius Gediminas Technical University. In order to develop a uniform cyclic strength and shakedown calculation procedure for critical threaded joints, a completely new calculation of a progressive profile change is recommended to be performed before the calculation of cyclic strength. The results have been used in the development of calculation standards for nuclear power equipment, in designing mineral grinding machines and evaluating their residual resource.

A Dynamic Measurement Model of Equipment Procurement Progress for Nuclear Power Project Based on EVM

2017 ◽  
Author(s):  
Ming Li ◽  
Hui Zhou ◽  
Rongxin Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dynamic Model ◽  
Nuclear Power ◽  
Cost Control ◽  
Measurement Model ◽  
Dynamic Measurement ◽  
Power Equipment ◽  
Nuclear Power Project ◽  
Power Project

A novel dynamic model and refined method for implementation of the Earned Value Management (EVM) on nuclear power equipment procurement is proposed in this paper. The EVM is known as an efficient and accurate method for progress and cost control in most of the civil engineering systems; however, there is lack of literatures on the EVM for precisely measuring the procurement progress in large-scale complex industrial projects, such as nuclear power plant systems. A novel dynamic measurement model based on the EVM is first established for evaluating the progress and performance of purchasing the nuclear power equipment, including specified details of operating procedure by quantitative valuing each schedule node based on work breaking-down structure (WBS) elements; then the dynamic model is analyzed and verified by a realistic contract of nuclear power equipment procurement. Furthermore, a nuclear power project under construction is studied and the equipment procurement progress is evaluated by applying the novel dynamic measurement model. Finally, the deviation of equipment procurement contract execution is presented by calculating the performance of progress and cost, which helps identify and analyze the delay risks. The dynamic measurement model has been applied in an abuilding nuclear power plant since January 2015, the results of applying the new model providing significant support to the progress and cost control of equipment procurement and bringing considerable profits to the project management. Based on the investigation and results of the above project, the new dynamic model is viable to be employed in future projects of nuclear power plant as a practical reference for applying the EVM in procurement management.

A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology

2017 ◽  
Author(s):  
Yi Xiao-jian ◽  
Lu Ming-chao ◽  
Mu Hui-na ◽  
Shi Jian ◽  
Hou Peng
Keyword(s):  
Nuclear Power ◽  
System Analysis ◽  
Reliability Assessment ◽  
Assessment Method ◽  
Power Equipment ◽  
Test Unit ◽  
New Approach ◽  
Electronic Control System ◽  
Go Model ◽  
Mean Time

This paper presents a new reliability assessment method for complex nuclear power equipment based on Goal Oriented (GO) method to evaluate Mean Time To Failures (MTTF). First, the new reliability assessment method is expounded in detail. And its process is formulated. Then, the electronic control system of hoisting mechanism in nuclear power plant is taken as an example to evaluate its MTTF by the new method. The reliability assessment processes are mainly as follows: (i) Conducting system analysis, (ii) Developing GO model, (iii) Selecting test unit by qualitative analysis of GO method, (iv) Collecting test data, (v) Estimating the failure rate of test unit, (vi) Evaluating system MTTF. In order to verify the advantages and rationality of the new reliability assessment method, the results are compared with the results by Monte Carlo method. All in all, this reliability assessment method not only improves the theory of GO method, which is only used to conduct reliability analysis before; but also provides a new approach for reliability assessment of complex nuclear power equipment, so than it can reduces costs, and improve estimating efficiency and accuracy.

Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS

2013 ◽  
Author(s):  
Rui Liu ◽  
Tie-ping Li ◽  
Ming-yu Wang
Keyword(s):  
High Pressure ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Safety Evaluation ◽  
Practical Method ◽  
Mechanical Analysis ◽  
Power Equipment ◽  
Pipe System ◽  
Finite Element Software ◽  
Class 1

In recent years, nuclear pipes play a very important role in the nuclear power equipment. Nuclear pipes especially class 1 usually contain cooling coolant of high temperature and high pressure in the operating nuclear power plant. The integrality of the nuclear pipes is very important to the nuclear reactor. This paper discusses the mechanical analysis and fatigue analysis of Class 1 pipes using finite element software. The soft ware PIPESTRESS is used to analysis the Class 1 pipe system to introduce the procedure for mechanical analysis and safety evaluation. The objective is to satisfy the criteria RCC-M. The results show that the pipe can guarantee the integrity of the pipe under the conditions. The method introduced in this paper can be used as a practical method for mechanical analysis of a nuclear Class 1 pipes.

Determining the power performance effect from modernization of power equipment and process systems at a nuclear power station

2012 ◽  
Vol 59 (5) ◽  
pp. 352-358 ◽  
Author(s):  
L. A. Khomenok ◽  
P. A. Kruglikov ◽  
Yu. V. Smolkin ◽  
K. V. Sokolov
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Equipment ◽  
Power Performance ◽  
Power Station ◽  
Performance Effect ◽  
Process Systems

scholarly journals PREDICTION OF OPERATION LIFE EXTENSION OF HEAT POWER EQUIPMENT

2020 ◽  
Vol 2 (61) ◽  
pp. 51-60
Author(s):  
V. Skalozubov ◽  
◽  
D. Pirkovsky ◽  
M. Alali ◽  
R. Algerby ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Accumulation Rate ◽  
Reactor Vessel ◽  
Life Extension ◽  
Normal Operation ◽  
Cyclic Loads ◽  
Power Equipment ◽  
Heat Power ◽  
Operation Conditions ◽  
Accident Conditions

Based on the analysis of known researches, it is revealed that the quantity and accumulation rate of cyclic thermal and dynamic loads in the transient modes of normal operation conditions, when violating normal operation conditions and in accident conditions (except for the nuclear reactor vessel) are the key factors of prediction of operation life extension for a heat power equipment (heat exchangers, pumps, armature). The method for predictive estimation of terms of operation life extension of a heat power equipment depending on stress amplitudes in transient and accident conditions, quantity and accumulation rate of cyclic loads, strength metal parameters of a heat power equipment vessels (except for a reactor vessel) is provided. The method is implemented on the example of steam generators of WWERs and using operational data of South-Ukraine-1 (by 2010). Admissible accumulation rate of cyclic loads during operation life extension by 30, 40 and 50 years is a result. The results define insufficient substantiation of nuclear power plant operation in the “maneuverable” modes with a variable reactor power. In this case, the quantity of cyclic equipment loads increases dramatically, and terms of safe operation are limited. The developed method and the obtained results of prediction of operation life extension of heat power equipment can be used for industry programs to extend the operation of Ukrainian nuclear power plants, as well as to improve the regulatory documents governing the conditions and requirements for acceptable safe extension of the operation life of heat power equipment of nuclear and thermal power enterprises. Further improvement of the method proposed in the work for predicting operation life extension of heat power equipment can be based on the development of methods for analyzing the reliability of heat power equipment and databases on operation disturbances.The materials of the presented work are used in the educational process for the training, retraining and advanced training of specialists in the energy industry.

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