Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants

Chi Yong Park; Yong Sung Lee; Myung Hwan Boo

doi:10.4028/www.scientific.net/KEM.297-300.1418

Paper Titles

Experimental Study on the Wear Behavior of Nuclear Fuel Rod in High Temperature Water Environment
p.1395

Effect of Micro-Addition Rare Earth and Chrome on Friction and Wear Behavior of Boronized Layer
p.1401

Finite Element Analysis of Fretting Wear Problems in Consideration of Frictional Contact
p.1406

Fretting Wear Characteristics of INCONEL 690 and INCONEL 600 in Water Environment
p.1412

Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants
p.1418

Wear Characteristics of INCONEL 690 and INCONEL 600 in Elevated Temperature
p.1424

Tribological Behavior of Multilayered WC-Ti1-xAlxN Coatings Deposited by Cathodic Arc Deposition Process on High Speed Steel
p.1430

Compression Characteristic and Tensile Property in an (Alpha+Beta)-Type Titanium Alloy at High Temperature
p.1439

Effect of Film Thickness on Fatigue Strength of TiAl Alloy Coated with TiAlN Film at Elevated Temperature
p.1446

HomeKey Engineering MaterialsKey Engineering Materials Vols. 297-300Development of Wear Test System for Steam...

Development of Wear Test System for Steam Generator Tubes in Nuclear Power Plants

Abstract:

In steam generators of nuclear power plants, flow-induced vibration (FIV) can lead to tube damage by fretting-wear occurred due to impact and sliding movement between the tubes and their supports. There have been many studies and test results on wear damage of steam generator tubes but they were not reflected the mechanical and chemical conditions accurately. KEPRI nuclear power laboratory developed a wear test system, which is able to control the motion of impact and sliding simultaneously in the pressurized high temperature water-chemistry conditions. Some wear tests were performed to verify the stable operation for the wear test. This wear test system with new concepts was described briefly, and some data for verifying its performance have been shown in the cases of the selected some test results. In the test, Alloy 690 was used for tube materials and 409 stainless steel for support plates. A little data deviation was obtained and stability of system operation was investigated.