Fracture behavior of austenitic stainless steels irradiated in PWR

Fukuya, Koji; Nishioka, Hiromasa; Fujii, K.; Kamaya, Masayuki; Miura, Terumitsu; Torimaru, Tadahiko

doi:10.1016/j.jnucmat.2008.06.028

Cited by 36 publications

(26 citation statements)

References 16 publications

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“…On the other hand, there was not yet any direct evidence for the fracture mechanism in irradiated ASSs even if the pure IG fractures observed at impact tests at −196 • C [17] might be the case. The fracture character of in-service irradiated 18Cr-10Ni-Ti [3] and CW316L of FTT [17] changed from fully ductile dimples at RT to 90% IG at very low temperature about −100 • C. Reasons for the change are not clear, nor is it clear whether IG fracture occurs by an atomically brittle mode (Type 1, Figure 1a) or by MVC process (Type 2, Figure 1b).…”

Section: Type 1-brittle Intergranular Fracturementioning

confidence: 94%

“…The other case [16,17] of the presence of IG fractures was observed on the specimens of flux thimble tubes (15%CW A316) at low and room temperatures in impact tests ( Figure 4). These FTTs were irradiated in 290-325 • C at PWR to doses from 11 to 73 dpa.…”

Section: Low Temperature Irradiationmentioning

confidence: 98%

“…These results indicated that the intergranular fracture occurrence was dependent on temperature and on specimen stress-strain state. In [17], a compilation of fracture data gathered on A304 and CWA316 irradiated steels was performed [15,17,[20][21][22][23][24][25][26]: it appeared that there are two different conditions for the occurrence of IG modes in stainless steels irradiated in PWRs: Low Temperature High strain Rate (LTHR) condition and High Temperature Low strain Rate (HTLR) condition. The sensitivity to IG mode was higher for higher doses in both conditions, and becomes higher for lower temperature in LTHR conditions and for higher temperature and lower strain rate in HTLR conditions.…”

Section: Low Temperature Irradiationmentioning

confidence: 99%

“…The fracture character of in-service irradiated 18Cr-10Ni-Ti [3] and CW316L of FTT [17] changed from fully ductile dimples at RT to 90% IG at very low temperature about −100 • C. Reasons for the change are not clear, nor is it clear whether IG fracture occurs by an atomically brittle mode (Type 1, Figure 1a) or by MVC process (Type 2, Figure 1b). In 18Cr-10Ni-Ti [3], the low T IG fracture occurred in all the three levels of irradiation.…”

Section: Type 1-brittle Intergranular Fracturementioning

confidence: 99%

“…Type 2a. As mentioned above, the IG fracture character of 18Cr-10Ni-Ti [3] and CW316L [17] at very low temperature below −100 • C may be explained by Type 1a as well or Type 2a mechanisms. For sure, the IG planes are not featureless and may contain very fine dimples.…”

Section: Type 2-ductile Intergranular Fracturementioning

confidence: 99%

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Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Hojná

2017

Metals

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Austenitic stainless steels are normally ductile and exhibit deep dimples on fracture surfaces. These steels can, however, exhibit brittle intergranular fracture under some circumstances. The occurrence of intergranular fracture in the irradiated steels is briefly reviewed based on limited literature data. The data are sorted according to the irradiation temperature. Intergranular fracture may occur in association with a high irradiation temperature and void swelling. At low irradiation temperature, the steels can exhibit intergranular fracture at low or even at room temperatures during loading in air and in high temperature water (~300 • C). This paper deals with the similarities and differences for IG fractures and discusses the mechanisms involved. The intergranular fracture occurrence at low temperatures might be correlated with decohesion or twinning and strain martensite transformation in local narrow areas around grain boundaries. The possibility of a ductile-to-brittle transition is also discussed. In case of void swelling higher than 3%, quasi-cleavage at low temperature might be expected as a consequence of ductile-to-brittle fracture changes with temperature. Any existence of the change in fracture behavior in the steels of present thermal reactor internals with increasing irradiation dose should be clearly proven or disproven. Further studies to clarify the mechanism are recommended.

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Section: Type 1-brittle Intergranular Fracturementioning

confidence: 94%

Section: Low Temperature Irradiationmentioning

confidence: 98%