International Research Journal of Engineering and Technology (IRJET) e-ISSN: 2395-0056 Volume: 05 Issue: 12 | Dec 2018 www.irjet.net p-ISSN: 2395-0072 © 2018, IRJET | Impact Factor value: 7.211 | ISO 9001:2008 Certified Journal | Page 1469 REVIEW ON VARIOUS PRACTICES ON FATIGUE ANALYSIS OF NUCLEAR POWER PLANT PIPING COMPONENTS Dinesh Agarwal, Dinesh Soni, S. K. Dhakad -----------------------------------------------------------------***------------------------------------------------------------------ ABSTRACT:- There are many causes of fatigue failures in in-service condition, of piping components in nuclear power plants. But variable loading conditions are more liable, hence is discussed in this paper. Characteristics, causes and applications of fatigue crack growth in nuclear power plants were discussed and reviewed. This article reviews literatures which were summarized to understand factors influencing crack growth rate, current techniques and traditional methods of fatigue crack growth rate, data generation and their numerical analysis published since 19 th century. Results from experimental studies, numerical analyses and computational datas via dissimilar sample geometries of pipes and loading situations are summarized and discussed. Keywords - NPP, FCG, LBB, J integral, SIF, FEM 1. INTRODUCTION Over last several years, various works have been done all through the globe to formulate a scheme oriented style for measurement of effect of fatigue in piping components of power plants. Piping components (pipes, elbows, joints), nozzles, valves and pumps in plants are structural components in a nuclear power plant (NPP) which are most prone to suffer from fatigue failures. Pipes and elbows are important components in piping systems. When elbow is subjected to variable loading, piping components are more liable to crack. The stress/strain concentrated at the internal and external surfaces of pipe- elbows at crown, intrados and extrados locations, which causes failures. The numbers of cycles of failures are not known in most of cases, but it has been assumed to be in the order of 10 7 cycles or more. To assess remaining life for the duration of in-service procedure of components, this makes more logic to chase the plant operational record as it proceeds. To pursue this approach, it is extremely essential to process in addition to manage the plant in service datas like that they will be use for an exhaustive fatigue analysis. Computerized system software which can assemble these necessities, were available commercially and applied for various parts in usual nuclear power plants. Rewards of these computerized systems are (i) give numbers to report for real fatigue load Manuscript received Dinesh Agrawal, mechanical, Govt. polytechnic Morena, M.P., India. Prof. Dinesh Soni, Mechanical engineering, RNTU, M.P., India. Dr. S. K. Dhakad,Mechanical engineering, SATI, Vidisha, M.P., India. (ii) Remaining life portion (iii) number of cycles for through wall crack (iv) additional trustworthy data base of piping system to apply for fatigue analyses for evaluation of damage mechanism or remaining life, together with ecological and load-history property. Hence, an add to in plant component presentation as well as better safety was anticipated.[1] August Wohler (1860-1870) studied and discussed failure system of locomotive axles; by means of apply restricted load cycles and even given theory of stress-number of cycles (i.e. S-N diagram) to calculate fatigue life. Spurred complete investigation work on this theme was done after a serious accident which was take place just about 20 th century. Fatigue is the principal mode of failure to be considered in the designing of components and different structures subjected to repetitive types of loads, e.g. automobile components, railway track components and rolling stock bridges. Offshore structures, ships, pressure vessels, handling equipment like cranes, excavators and pipelines, aircraft and space structures are some of the components/ structures, which are generally subjected to repetitive loads during their lifetime.[2] Many experimental, numerical, analytical along with comparative study was done on pipes and pipe elbows having circumferential inner or outer surface cracks or through wall cracks to evaluate J-integral and collapse load. Works of a number of researchers have been summarized here to understand methods used to analysis of fatigue failure especially in pipe and piping components present in nuclear power plants.