Developing an Empirical Relationship to Predict the Wear Characteristics of Ni-Based Hardfaced Deposits on Nuclear Grade 316LN Austenitic Stainless Steel

S Gnanasekaran,Ramesh Arthanari,G Padmanaban,Samson Jerold Samuel Chelladurai,V Balasubramanian,Alicia E Ares

doi:10.1155/2021/3934787

S Gnanasekaran, Ramesh Arthanari + Show 4 more

Open Access

https://doi.org/10.1155/2021/3934787

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Abstract

Using the nickel-based Colmonoy 5 hardfacing alloy, components made of austenitic stainless steel (ASS) used in nuclear power plants can be hardfaced. Hardfacing is the process of applying complex and wear-resistant materials to substrates that require abrasion resistance. The tribological characteristics of a reactor-grade material NiCr-B hardfaced deposit were studied and reported in this paper. Hence, in this investigation, an effort has been made to develop empirical relationship to predict weight loss of laser hardfaced Ni-based alloy surface incorporating laser parameters using statistical tools such as design of experiments (DoE) and analysis of variance (ANOVA). The developed empirical relationship can be effectively used to trail the weight loss (wear resistance) of laser hardfaced nickel alloy surfaces by altering laser parameters. This method has proven very effective. A power of 1300 W, powder feed rate of 9 g/min, travel speed of 350 mm/min, and defocusing distance of 32 mm were all combined to achieve a minimum weight loss of 0.0164 grams.

Highlights

Introduction eIndian prototype fast breeder reactor (PFBR) is a pooltype liquid sodium-cooled reactor with two independent sodium circuits, with the intermediate heat exchanger (IHX) allowing thermal contact between the main pool and the auxiliary circuit. ermal exchange occurs between the IHX and a steam generator (SG), which powers conventional steam turbines via the use of auxiliary sodium circuits
Using the nickel-based Colmonoy 5 hardfacing alloy, components made of austenitic stainless steel (ASS) used in nuclear power plants can be hardfaced
Introduction e Indian prototype fast breeder reactor (PFBR) is a pooltype liquid sodium-cooled reactor with two independent sodium circuits, with the intermediate heat exchanger (IHX) allowing thermal contact between the main pool and the auxiliary circuit. ermal exchange occurs between the IHX and a steam generator (SG), which powers conventional steam turbines via the use of auxiliary sodium circuits

Summary

Research Article

Using the nickel-based Colmonoy 5 hardfacing alloy, components made of austenitic stainless steel (ASS) used in nuclear power plants can be hardfaced. E tribological characteristics of a reactor-grade material NiCr-B hardfaced deposit were studied and reported in this paper In this investigation, an effort has been made to develop empirical relationship to predict weight loss of laser hardfaced Ni-based alloy surface incorporating laser parameters using statistical tools such as design of experiments (DoE) and analysis of variance (ANOVA). E developed empirical relationship can be effectively used to trail the weight loss (wear resistance) of laser hardfaced nickel alloy surfaces by altering laser parameters. An effort has been made to develop an empirical connection to forecast wear resistance of hardfaced alloy deposits utilizing statistical methods, such as experimental design, variance analysis, and regression analysis, integrating major laser surface characteristics. Before and after each trial, the specimen was carefully cleaned in alcohol and gently dried, and the weight loss was quantified to an accuracy of 0.001 mg before and after each test

Pores e increased energy density per unit of measurement

Findings

Conclusions