원전 내부구조물 오스테나이트 스테인리스강 용접부의 열시효 거동 및 열취화 활성화에너지 분석

This study examines the thermal aging behavior and associated changes in mechanical properties of austenitic stainless steel welds (ASSW) used within reactor vessel internals (RVI). ASSW specimens were fabricated employing the Gas Tungsten Arc Welding (GTAW) technique, adhering to the welding proced...

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Published in대한금속·재료학회지, 63(5) Vol. 63; no. 5; pp. 330 - 343
Main Authors 김유진, Yoojin Kim, 김지수, Ji-su Kim, 서주원, Joowon Suh, 김종민, Jongmin Kim, 이수열, Soo Yeol Lee, 홍석민, Seokmin Hong
Format Journal Article
LanguageKorean
Published 대한금속재료학회 01.05.2025
대한금속·재료학회
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ISSN1738-8228
2288-8241
DOI10.3365/KJMM.2025.63.5.330

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Abstract This study examines the thermal aging behavior and associated changes in mechanical properties of austenitic stainless steel welds (ASSW) used within reactor vessel internals (RVI). ASSW specimens were fabricated employing the Gas Tungsten Arc Welding (GTAW) technique, adhering to the welding procedure specifications for RVI, and were thermally aged at 340℃, 400℃, and 450℃ for durations up to 15,000 hours. Assessments included strength, impact toughness, and delta-ferrite hardness, while thermal embrittlement activation energy was estimated using nano-indentation combined with the Cahn- Hilliard model. Microstructural analysis revealed a delta-ferrite content of approximately 7%, which appeared as fine dendritic structures (thickness <2 μm) within the austenite matrix. Spinodal decomposition in the delta-ferrite led to the formation of Cr-rich α′ phases at all thermal aging temperatures, with a noted increase in Cr concentration over time. Upon aging at 340℃ for 14,000 hours, Ni-rich clusters were observed, indicating that extended aging could be necessary for G-phase precipitation at lower temperatures. Conversely, Ni-rich precipitates identified as a face-centered cubic (FCC) G-phase emerged in delta-ferrite aged at 400℃ and 450℃. The absence of Cr carbide precipitation supports a consistent aging mechanism across the 340-450℃ range. Aging resulted in a slight increase in tensile strength, a decrease in elongation, and a significant reduction in impact toughness. Nano-indentation confirmed an increase in delta-ferrite hardness, which was normalized using the austenite-to-delta-ferrite hardness ratio. Activation energy for thermal embrittlement was calculated to be 100 kJ/mol for the 340- 400℃ range and 77 kJ/mol for the 340-450℃ range. (Received 18 March, 2025; Accepted 9 April, 2025)
AbstractList This study examines the thermal aging behavior and associated changes in mechanicalproperties of austenitic stainless steel welds (ASSW) used within reactor vessel internals (RVI). ASSWspecimens were fabricated employing the Gas Tungsten Arc Welding (GTAW) technique, adhering to thewelding procedure specifications for RVI, and were thermally aged at 340°C, 400°C, and 450°C for durationsup to 15,000 hours. Assessments included strength, impact toughness, and delta-ferrite hardness, whilethermal embrittlement activation energy was estimated using nano-indentation combined with the Cahn-Hilliard model. Microstructural analysis revealed a delta-ferrite content of approximately 7%, whichappeared as fine dendritic structures (thickness <2 μm) within the austenite matrix. Spinodaldecomposition in the delta-ferrite led to the formation of Cr-rich α′ phases at all thermal agingtemperatures, with a noted increase in Cr concentration over time. Upon aging at 340°C for 14,000 hours,Ni-rich clusters were observed, indicating that extended aging could be necessary for G-phase precipitationat lower temperatures. Conversely, Ni-rich precipitates identified as a face-centered cubic (FCC) G-phaseemerged in delta-ferrite aged at 400°C and 450°C. The absence of Cr carbide precipitation supports aconsistent aging mechanism across the 340–450°C range. Aging resulted in a slight increase in tensilestrength, a decrease in elongation, and a significant reduction in impact toughness. Nano-indentationconfirmed an increase in delta-ferrite hardness, which was normalized using the austenite-to-delta-ferritehardness ratio. Activation energy for thermal embrittlement was calculated to be 100 kJ/mol for the 340–400°C range and 77 kJ/mol for the 340–450°C range. KCI Citation Count: 0
This study examines the thermal aging behavior and associated changes in mechanical properties of austenitic stainless steel welds (ASSW) used within reactor vessel internals (RVI). ASSW specimens were fabricated employing the Gas Tungsten Arc Welding (GTAW) technique, adhering to the welding procedure specifications for RVI, and were thermally aged at 340℃, 400℃, and 450℃ for durations up to 15,000 hours. Assessments included strength, impact toughness, and delta-ferrite hardness, while thermal embrittlement activation energy was estimated using nano-indentation combined with the Cahn- Hilliard model. Microstructural analysis revealed a delta-ferrite content of approximately 7%, which appeared as fine dendritic structures (thickness <2 μm) within the austenite matrix. Spinodal decomposition in the delta-ferrite led to the formation of Cr-rich α′ phases at all thermal aging temperatures, with a noted increase in Cr concentration over time. Upon aging at 340℃ for 14,000 hours, Ni-rich clusters were observed, indicating that extended aging could be necessary for G-phase precipitation at lower temperatures. Conversely, Ni-rich precipitates identified as a face-centered cubic (FCC) G-phase emerged in delta-ferrite aged at 400℃ and 450℃. The absence of Cr carbide precipitation supports a consistent aging mechanism across the 340-450℃ range. Aging resulted in a slight increase in tensile strength, a decrease in elongation, and a significant reduction in impact toughness. Nano-indentation confirmed an increase in delta-ferrite hardness, which was normalized using the austenite-to-delta-ferrite hardness ratio. Activation energy for thermal embrittlement was calculated to be 100 kJ/mol for the 340- 400℃ range and 77 kJ/mol for the 340-450℃ range. (Received 18 March, 2025; Accepted 9 April, 2025)
Author 김종민
홍석민
Seokmin Hong
김유진
Yoojin Kim
Soo Yeol Lee
Joowon Suh
Jongmin Kim
이수열
Ji-su Kim
서주원
김지수
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Analysis of Thermal Aging Behavior and Activation Energy of Austenitic Stainless Steel Weld for Reactor Vessel Internal
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Snippet This study examines the thermal aging behavior and associated changes in mechanical properties of austenitic stainless steel welds (ASSW) used within reactor...
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SubjectTerms activation energy
austenite stainless steel weld
delta-ferrite
nano-indentation test
thermal embrittlement
재료공학
Title 원전 내부구조물 오스테나이트 스테인리스강 용접부의 열시효 거동 및 열취화 활성화에너지 분석
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