Corrosion Fatigue Behavior of 316LN Stainless Steel Hollow Specimen in High-Temperature Pressurized Water

doi:10.11900/0412.1961.2020.00134

Acta Metall Sin

2021, Vol. 57

Issue (3): 309-316 DOI: 10.11900/0412.1961.2020.00134

Research paper

Current Issue | Archive | Adv Search

Corrosion Fatigue Behavior of 316LN Stainless Steel Hollow Specimen in High-Temperature Pressurized Water

TAN Jibo, WANG Xiang, WU Xinqiang(

), HAN En-Hou

CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China

Cite this article:

TAN Jibo, WANG Xiang, WU Xinqiang, HAN En-Hou. Corrosion Fatigue Behavior of 316LN Stainless Steel Hollow Specimen in High-Temperature Pressurized Water. Acta Metall Sin, 2021, 57(3): 309-316.

Download:

HTML

PDF(2748KB)
Export: BibTeX | EndNote (RIS)

Abstract

Environmentally assisted fatigue is an important factor in the design, safety review, and life management of key components used in nuclear power plants. Piping systems, valves, and small-bore pipes are sensitive to fatigue damage in nuclear power plants. In this work, a kind of hollow specimen for fatigue testing was designed. High-temperature pressurized water flows through the inside of the specimen, and the outside of the specimen is exposed to air. The corrosion fatigue behavior of 316LN stainless steel was investigated in high-temperature pressurized water using the hollow specimens. The experimental results show that the fatigue strength of 316LN stainless steel was reduced in a high-temperature pressurized water environment, and its fatigue life decreased with decreasing strain rate. The fatigue lives obtained by hollow and standard round bar specimens were comparable, which indicate that it is reasonable and feasible to use the hollow specimen to study the environmentally assisted fatigue performance of nuclear-grade structural materials in a high-temperature pressurized water environment. At low strain rate conditions, the fatigue crack initiation region is a typical fan-shaped pattern with quasi-cleavage cracking characteristics. The fatigue crack growth region is characterized by fatigue striation, and the environmental effects are highly significant in the stage of fatigue crack initiation. The fatigue damage mechanism of 316LN stainless steel in a high-temperature pressurized water environment is also discussed.

Key words: corrosion fatigue high-temperature pressurized water stainless steel hollow specimen

Received: 27 April 2020

ZTFLH:

TL341

Fund: National Key Research and Development Program of China(2017YFB0702103);National Natural Science Foundation of China(51671201)

	Service

	E-mail this article
	Add to citation manager
	E-mail Alert
	RSS
	（）
	Articles by authors
	Jibo TAN
	Xiang WANG
	Xinqiang WU
	En-Hou HAN

URL:

https://www.ams.org.cn/EN/10.11900/0412.1961.2020.00134 OR https://www.ams.org.cn/EN/Y2021/V57/I3/309

Fig.1 Schematic of shape and size of 316LN stainless steel hollow specimen (unit: mm)

Fig.2 Schematic of high-temperature pressurized circulating water corrosion fatigue device (DO—dissolved oxygen, Con—conductivity)

Fig.3 Installation of 316LN stainless steel hollow specimen

Table 1 Corrosion fatigue test parameters

Fig.4 OM image of microstructure of 316LN stainless steel

Fig.5 Corrosion fatigue data of 316LN stainless steel hollow specimen and standard round bar specimen^[13] in high-temperature pressurized water

Fig.6 The effect of strain rate on fatigue life of 316LN stainless steel hollow specimen

Fig.7 Relationships between peak load and number of cycles for 316LN stainless steel fatigue tested in high-temperature pressurized water

Fig.8 Macromorphologies of fatigue fractures of 316LN stainless steel hollow specimens at different strain rates

Fig.9 Morphologies of fatigue crack initiation sites of 316LN stainless steel hollow specimens at different strain rates (a, c, e), and corresponding enlarged views of marked positions (b, d, f )

Fig.10 Fatigue striation characteristics at different fracture locations (distance from crack initiation site) of 316LN stainless steel hollow specimens at different strain rates of 0.4 × 10^-2 s^-1 (a, d, g), 0.04 × 10^-2 s^-1 (b, e, h), and 0.004 × 10^-2 s^-1 (c, f, i) (The line in the figure dencotes the fatigue crack propagation direction, and the number is the average fatigue striation spacing in the line length area, unit: μm/cyc)

Fig.11 Morphology of secondary cracks (a) and oxides (b) on inner surface of 316LN stainless steel hollow specimen

Fig.12 The fatigue crack growth rate (da/dN) at different distances to crack initiation sites for 316LN stainless steel in high-temperature pressurized water

1	Carey J. Materials reliability program, fatigue issues assessment (MRP-138) [R]. Electric Power Research Institute, 2005
2	Chopra O K, Shack W J. Effect of LWR coolant environments on the fatigue life of reactor materials [R]. NUREG/CR-6909, ANL-06/08, 2007
3	Chopra O K, Stevens G. Effect of LWR coolant environments on the fatigue life of reactor materials [R]. NUREG/CR-6909, 2018
4	Japan Nuclear Energy Safety Organization. Environmental fatigue evaluation method for nuclear power plants [R]. JNES-SS-1005, 2011
5	Kondo T, Nakajima H, Nagasaki R. Metallographic investigation on the cladding failure in the pressure vessel of a BWR [J]. Nucl. Eng. Des., 1971, 16: 205
6	US Nuclear Regulatory Commission (NRC). Regulatory Guide 1.207, Guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors [Z]. Washington DC, USA: Nuclear Regulatory Commission, 2007
7	Tan J B, Wu X Q, Han E H, et al. Strain-rate dependent fatigue behavior of 316LN stainless steel in high-temperature water [J]. J. Nucl. Mater., 2017, 489: 33
8	Wu X Q, Xu S, Han E H, et al. Corrosion fatigue of nuclear-grade stainless steel in high temperature water and its environmental fatigue design model [J]. Acta Metall. Sin., 2011, 47: 790
	吴欣强, 徐松, 韩恩厚等. 核级不锈钢高温水腐蚀疲劳机制及环境疲劳设计模型 [J]. 金属学报, 2011, 47: 790
9	American Society of Mechanical Engineers. ASME boiler and pressure vessel code section III (Z), New York, 2015
10	Faidy C. Status of French road map to improve environmental fatigue rules [A]. Proceedings of the ASME 2012 Pressure Vessels and Piping Conference [C]. Toronto, Ontario, Canada: ASME, 2012
11	American Society Mechanical Engineers. Fatigue design curves for light water reactor environments [Z]. ASME Code-Case N-761, 2010
12	American Society Mechanical Engineers. Fatigue evaluations including environmental effects [Z]. ASME Code-Case N-792, 2010
13	Tan J B, Zhang Z Y, Zheng H, et.al. Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants [J]. J. Nucl. Mater., 2020, 541, 152407
14	Cho H, Kim B K, Kim I S, et al. Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310℃ deaerated water-fatigue life and dislocation structure development [J]. Mater. Sci. Eng., 2008, A476: 248
15	Hong S G, Lee S B. Mechanism of dynamic strain aging and characterization of its effect on the low-cycle fatigue behavior in type 316L stainless steel [J]. J. Nucl. Mater., 2005, 340: 307
16	Hong S G, Lee S B. Dynamic strain aging under tensile and LCF loading conditions, and their comparison in cold worked 316L stainless steel [J]. J. Nucl. Mater., 2004, 328: 232
17	Kuang W J, Wu X Q, Han E H. Influence of dissolved oxygen concentration on the oxide film formed on 304 stainless steel in high temperature water [J]. Corros. Sci., 2012, 63: 259
18	Gavenda D J, Luebbers P R, Chopra O K. Crack initiation and crack growth behavior of carbon and low-alloy steels [R]. Orlando, FL: ASME, 1997: 243
19	Gao J, Tan J B, Wu X Q, et al. Effect of grain boundary engineering on corrosion fatigue behavior of 316LN stainless steel in borated and lithiated high-temperature water [J]. Corro. Sci., 2019, 152: 190
20	Chopra O K, Park H B. Mechanism of fatigue crack initiation in light water reactor coolant environments [R]. ANL/ET/CP-101178, 2000
21	Huin N, Tsutusmi K, Legras L, et al. Fatigue crack initiation of 304L stainless steel in simulated PWR primary environment: Relative effect of strain rate [A]. Proceedings of the ASME 2012 Pressure Vessels and Piping Conference [C]. Toronto, Ontario, Canada: ASME, 2012
22	Xu S, Wu X Q, Han E H, et al. Crack initiation mechanisms for low cycle fatigue of type 316Ti stainless steel in high temperature water [J]. Mater. Sci. Eng., 2008, A490: 16
23	Turnbull A. Modelling of crack chemistry in sensitized stainless steel in boiling water reactor environments [J]. Corros. Sci., 1997, 39: 789
24	Turnbull A. Modeling of the chemistry and electrochemistry in cracks—A review [J]. Corrosion, 2001, 57: 175
25	Dumerval M, Perrin S, Marchetti L, et al. Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of pressurized water reactor (PWR) [J]. Corros. Sci., 2014, 85: 251
26	Jambon F, Marchetti L, Jomard F, et al. Mechanism of hydrogen absorption during the exposure of alloy 600-like single-crystals to PWR primary simulated media [J]. J. Nucl. Mater., 2011, 414: 386
27	Laird C, Smith G C. Crack propagation in high stress fatigue [J]. Philo. Mag., 1962, 7: 847
28	Zhang Z Y, Tan J B, Wu X Q, et al. Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water [J]. J. Nucl. Mater., 2019, 518: 21
29	Kanezaki T, Narazaki C, Mine Y, et al. Effects of hydrogen on fatigue crack growth behavior of austenitic stainless steels [J]. Int. J. Hydrogen Energy, 2008, 33: 2604

[1]	HOU Juan, DAI Binbin, MIN Shiling, LIU Hui, JIANG Menglei, YANG Fan. Influence of Size Design on Microstructure and Properties of 304L Stainless Steel by Selective Laser Melting[J]. 金属学报, 2023, 59(5): 623-635.
[2]	WANG Bin, NIU Mengchao, WANG Wei, JIANG Tao, LUAN Junhua, YANG Ke. Microstructure and Strength-Toughness of a Cu-Contained Maraging Stainless Steel[J]. 金属学报, 2023, 59(5): 636-646.
[3]	WU Xinqiang, RONG Lijian, TAN Jibo, CHEN Shenghu, HU Xiaofeng, ZHANG Yangpeng, ZHANG Ziyu. Research Advance on Liquid Lead-Bismuth Eutectic Corrosion Resistant Si Enhanced Ferritic/Martensitic and Austenitic Stainless Steels[J]. 金属学报, 2023, 59(4): 502-512.
[4]	HAN En-Hou, WANG Jianqiu. Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials[J]. 金属学报, 2023, 59(4): 513-522.
[5]	CHANG Litao. Corrosion and Stress Corrosion Crack Initiation in the Machined Surfaces of Austenitic Stainless Steels in Pressurized Water Reactor Primary Water： Research Progress and Perspective[J]. 金属学报, 2023, 59(2): 191-204.
[6]	WEN Donghui, JIANG Beibei, WANG Qing, LI Xiangwei, ZHANG Peng, ZHANG Shuyan. Microstructure Evolution at Elevated Temperature and Mechanical Properties of MoNb-Modified FeCrAl Stainless Steel[J]. 金属学报, 2022, 58(7): 883-894.
[7]	ZHENG Chun, LIU Jiabin, JIANG Laizhu, YANG Cheng, JIANG Meixue. Effect of Tensile Deformation on Microstructure and Corrosion Resistance of High Nitrogen Austenitic Stainless Steels[J]. 金属学报, 2022, 58(2): 193-205.
[8]	YUAN Jiahua, ZHANG Qiuhong, WANG Jinliang, WANG Lingyu, WANG Chenchong, XU Wei. Synergistic Effect of Magnetic Field and Grain Size on Martensite Nucleation and Variant Selection[J]. 金属学报, 2022, 58(12): 1570-1580.
[9]	LUO Wenze, HU Long, DENG Dean. Numerical Simulation and Development of Efficient Calculation Method for Residual Stress of SUS316 Saddle Tube-Pipe Joint[J]. 金属学报, 2022, 58(10): 1334-1348.
[10]	PAN Qingsong, CUI Fang, TAO Nairong, LU Lei. Strain-Controlled Fatigue Behavior of Nanotwin- Strengthened 304 Austenitic Stainless Steel[J]. 金属学报, 2022, 58(1): 45-53.
[11]	CAO Chao, JIANG Chengyang, LU Jintao, CHEN Minghui, GENG Shujiang, WANG Fuhui. Corrosion Behavior of Austenitic Stainless Steel with Different Cr Contents in 700^oC Coal Ash/High Sulfur Flue-Gas Environment[J]. 金属学报, 2022, 58(1): 67-74.
[12]	AN Xudong, ZHU Te, WANG Qianqian, SONG Yamin, LIU Jinyang, ZHANG Peng, ZHANG Zhaokuan, WAN Mingpan, CAO Xingzhong. Interaction Mechanism of Dislocation and Hydrogen in Austenitic 316 Stainless Steel[J]. 金属学报, 2021, 57(7): 913-920.
[13]	CHEN Guo, WANG Xinbo, ZHANG Renxiao, MA Chengyue, YANG Haifeng, ZHOU Li, ZHAO Yunqiang. Effect of Tool Rotation Speed on Microstructure and Properties of Friction Stir Processed 2507 Duplex Stainless Steel[J]. 金属学报, 2021, 57(6): 725-735.
[14]	WANG Jinliang, WANG Chenchong, HUANG Minghao, HU Jun, XU Wei. The Effects and Mechanisms of Pre-Deformation with Low Strain on Temperature-Induced Martensitic Transformation[J]. 金属学报, 2021, 57(5): 575-585.
[15]	HUANG Yichuan, WANG Qing, ZHANG Shuang, DONG Chuang, WU Aimin, LIN Guoqiang. Optimization of Stainless Steel Composition for Fuel Cell Bipolar Plates[J]. 金属学报, 2021, 57(5): 651-664.

No Suggested Reading articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed