Study on Low Temperature Thermal Aging Behavior of 316LN Austenitic Stainless Steel Weld

Luo Qiang; CheN Yong; Qiu Shaoyu; Zhou Jun; He Kun

doi:10.13832/j.jnpe.2014.04.0102

Volume 35 Issue 4

Feb. 2025

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Luo Qiang, CheN Yong, Qiu Shaoyu, Zhou Jun, He Kun. Study on Low Temperature Thermal Aging Behavior of 316LN Austenitic Stainless Steel Weld[J]. Nuclear Power Engineering, 2014, 35(4): 102-105. doi: 10.13832/j.jnpe.2014.04.0102

Citation:

Luo Qiang, CheN Yong, Qiu Shaoyu, Zhou Jun, He Kun. Study on Low Temperature Thermal Aging Behavior of 316LN Austenitic Stainless Steel Weld[J]. Nuclear Power Engineering, 2014, 35(4): 102-105. doi: 10.13832/j.jnpe.2014.04.0102

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Study on Low Temperature Thermal Aging Behavior of 316LN Austenitic Stainless Steel Weld

doi: 10.13832/j.jnpe.2014.04.0102

National Key Laboratory for Nuclear Fuel and Materials of Nuclear Power Institute of China, Chengdu 610041, China

Received Date: 2014-01-26
Rev Recd Date: 2014-04-26

Available Online: 2025-02-15

Abstract

Abstract

Austenitic stainless steel welds in PWR main pipe are susceptible to thermal aging embrittlement at reactor operating temperature of 280~325 ℃after a long service life.In order to obtain thermal aging embrittlement of 316 LN austenitic stainless steel weld at reactor operating temperature, In this study, thermal aging embrittlement of types 316 LN austenitic stainless steel weld with 10.7% ferrite was investigated on basis of embrittlement properties after aging up to 6,000 h at 325,365 and 400℃. The result show that,no change in the main alloy elements contents in ferrite and austenite.Large increase in the microhardness of weld was observed with no change in austenite hardness. The impact toughness was significantly degraded after aging.
- Thermal aging embrittlement,
- Austenitic stainless steel,
- Microhardness,
- Impact toughness