The Study on Effects of Thermal Aging of Dissimilar Weld Zone in a Primary Reactor Cooling System |
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| Journal | Key Engineering Materials (Volumes 261 - 263) |
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| Volume | Advances in Fracture and Failure Prevention |
| Edited by | Kikuo Kishimoto, Masanori Kikuchi, Tetsuo Shoji and Masumi Saka |
| Pages | 1689-0 |
| DOI | 10.4028/www.scientific.net/KEM.261-263.1689 |
| Citation | Jae Do Kwon et al., 2004, Key Engineering Materials, 261-263, 1689 |
| Online since | April, 2004 |
| Authors | Jae Do Kwon, Seung Wan Woo, Y.H. Choi |
| Keywords | Dissimilar Weld, Duplex Stainless Steel, Heat Affected Zone (HAZ), Low Alloy Steel, Mechanical Properties, Thermal Aging |
| Abstract | In a primary reactor cooling system(RCS), a dissimilar weld zone exists between austenitic-ferritic duplex cast stainless steel(CF8M) in a pipe and low-alloy steel(SA508 cl.3) in a nozzle. Thermal aging is observed in CF8M as the RCS is exposed for a long period of time to a reactor operating temperature between 290 and 330℃, while no effect is observed in SA508 cl.3. An investigation of the effect of thermal aging on the various mechanical properties of the dissimilar weld zone is required. The purpose of the present investigation is to find the effect of thermal aging on the dissimilar weld zone. The specimens are prepared by an artificially accelerated aging technique maintained for 100, 300, 900, 1800 and 3600 hrs at 430℃, respectively. The various mechanical tests for the dissimilar weld zone are performed for virgin and aged specimens. |
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