Environmentally assisted crack growth in 308L stainless steel weld metal in simulated primary water

Dong, Lijun; Han, En‐Hou; Peng, Qunjia; Ke, Wei; Wang, Lei

doi:10.1016/j.corsci.2016.12.011

Cited by 50 publications

(6 citation statements)

References 24 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The variation trend of δ phase in Figure 12 was consistent with the pitting corrosion resistance level reflected in Figure 15 and the IASCC resistance level reflected in Figure 6, that is, the 2 dpa sample containing the highest δ content had the best pitting and IASCC resistance. One possible reason was that the Cr-rich δ phase promoted the formation of Cr2O3 [33,39,44,[51][52][53] . The other reason was that the Ti element in the δ phase preferentially combined with C to form TiC to avoid the precipitation of CrC [1] , which further improved the pitting resistance.…”

Section: Reason Analysis Of Difference In Corrosion Resistancementioning

confidence: 99%

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

Gao,

Cao,

et al. 2023

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

The impacts of low dose irradiation on the behavior of electrochemical corrosion and irradiation assisted stress corrosion cracking for 321 stainless steel were studied using Fe2+ ion irradiation to simulate neutron radiation damage in primary circuit environment of pressurized water reactor. Low dose irradiation can improve the pitting resistance and reduce the cracking tendency of the alloy in B-Li solution to a certain extent, which was related to the δ phase content on the near-surface of the sample: The higher δ phase content on the near-surface of the 2 dpa irradiated sample was observed by grazing incident X-ray diffraction. In addition, the pits was significantly increased near micro-cracks for the unirradiated sample, indicating that the existence of pits induced the initiation of cracks. The research results provided an important reference for the failure mechanism of irradiation assisted stress corrosion cracking of core components.

show abstract

Section: Reason Analysis Of Difference In Corrosion Resistancementioning

confidence: 99%

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

Gao,

Cao,

et al. 2023

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

show abstract

“…It indicates that the involvement of corrosive medium or the interactions of corrosive medium with applied load might be responsible for the decrease in the fatigue life of the Z3CN20.09M ASS [16,17]. At the same strain amplitude, the decrease in strain rate yielded a lower fatigue life [15,[18][19][20][21]. For example, at 0.8% strain amplitude, the decrease in strain rate from 0.04% to 0.004%/s led to 3.5 times lower in the fatigue life.…”

Section: Fatigue Lifementioning

confidence: 99%

“…Furthermore, the difference in the fatigue life at these three strain rates became more pronounced at higher strain amplitude. It might be caused by the higher corrosion rate of the tested material at higher strain amplitude in the autoclave environments [6,[13][14][15][16][17][18][19][20][21][22][23][24][25][26][27].…”

Section: Fatigue Lifementioning

confidence: 99%

Environmental Fatigue Behavior of a Z3CN20.09M Stainless Steel in High Temperature Water

et al. 2022

Self Cite

View full text Add to dashboard Cite

The low-cycle fatigue behavior of a Z3CN20.09M austenitic stainless steel was investigated and its fatigue life in high temperature water was compared to that in the air at room temperature. It is found that the fatigue life in water at 300 °C was shorter than that in air, and it decreased with the decreasing strain rate from 0.4% to 0.004%/s. The ductile striations having streamed down features were observed at the strain rate of 0.004%/s, indicating that Z3CN20.09M austenitic stainless steel experienced anodic dissolution. The fatigue life obtained in the present experiment was consistent with that using prediction models.

show abstract

“…During the welding and service process of such structures, flaws such as cracks may occur in DMWJs due to the influence of microstructure and mechanical property inhomogeneity. It is demonstrated in several experiences of nuclear power plants (NPPs) that the weld zone is more susceptible to stress corrosion cracking (SCC) caused by hydrochemistry, material, and mechanical factors, which seriously threatens the safe operation of in-service NPPs [6][7][8][9][10], as shown in Figure 1. erefore, it is great to assess structural integrity accurately for such DMWJs with cracks.…”

Section: Introductionmentioning

confidence: 99%

Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel

Sun

Xue

Yang

et al. 2022

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

The material mechanical properties and crack propagation behavior of dissimilar metal welded joint (DMWJ) of pressurized water reactor (PWR) was investigated. In this research, the mechanical parameters of the cladding layer materials (304L-SA508) of the DMWJ in PWRs were obtained by the continuous indentation test. Simultaneously, the user-defined (USDFLD) subroutine in ABAQUS was used to establish the heterogeneous materials model of the welded joint. On this basis, the local crack propagation path of DMWJs has been discussed based on the extended finite element method (XFEM). The result indicated that the strength value at the fusion boundary line (FB line) is the largest, and the yield strength reaches 689 MPa. The yield stress values of the cladding metal (304 L) and base metal (SA508) are 371 MPa and 501 MPa, respectively. Affected by the material constraint effect of the DMWJ, the crack will propagate through the FB line when the initial crack is perpendicular to the FB line. And when the initial crack parallels the FB line, the crack will deviate from it. Meanwhile, the crack propagation length is smaller as the initial crack tip is closer to the FB line when the load condition is constant.

show abstract

Environmentally assisted crack growth in 308L stainless steel weld metal in simulated primary water

Cited by 50 publications

References 24 publications

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

Environmental Fatigue Behavior of a Z3CN20.09M Stainless Steel in High Temperature Water

Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel

Contact Info

Product

Resources

About