Evolution of the radiation-induced defect structure in 316 type stainless steel after post-irradiation annealing

Renterghem, W. Van; Konstantinović, M.J.; Vankeerberghen, Marc

doi:10.1016/j.jnucmat.2014.04.024

Cited by 29 publications

(8 citation statements)

References 29 publications

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“…Electron irradiation experiment for 316L resulted in the formation of a high number density of Frank loops, voids, and interstitial type black dots. The values of measured size and number density of each feature seemed to be reasonable compared with previous studies [15,[19][20][21][22]. Generally, neutron irradiation to 316L at relatively low temperature produced a high number density (<10 23 m -3 ) of very small defect clusters: black dots and voids (<3 nm).…”

Section: Discussionsupporting

confidence: 85%

“…PIA had less effect on recovery for BWR conditions due to thermally-sensitization during annealing, but a clear effect on microstructure and hardness for PWR conditions [17]. The PIA experiments were previously performed on 304 [17,18] and 316 [15,19] type stainless steels irradiated to moderate doses of 25 dpa and on 316 CW type stainless steel irradiated in a commercial reactor to 80 dpa [20]. In this paper, we are focusing on microstructure change in 316L and A533B, which is used as shroud and pressure vessel in Light Water Reactor (LWR), at the low doses of 1 dpa by electron beam irradiation.…”

Section: Introductionmentioning

confidence: 99%

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Annealing effect on microstructural recovery in 316L and A533B

Hashimoto

Goto

Inoue

et al. 2017

Journal of Nuclear Materials

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An austenitic model alloy (316L) and a low alloy steel (A533B) were exposed to constant or fluctuating temperature after electron irradiation to a cumulative damage level of 1 displacement per atom. 316L model alloy was exposed to LWR operating temperature during electron irradiation, and were exposed to a higher temperature at a high heating and cooling rates. The annealing experiment after irradiation to 316L resulted in the change in irradiation-induced microstructure; both the size and the number density of Frank loop and black dots were decreased, while the volume fraction of void was increased. In the case of A533B, the aging experiment after electron irradiation resulted in the shrinkage or the disappearance of black dots and the growth of dislocation loops. It is suggested that during annealing and/or aging at a high temperature the excess vacancies could be provided and flew into each defect feature, resulting in that interstitial type feature could be diminished, while vacancy type increased in volume fraction if exists.

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Section: Discussionsupporting

confidence: 85%

Section: Introductionmentioning

confidence: 99%

Annealing effect on microstructural recovery in 316L and A533B

Hashimoto

Goto

Inoue

et al. 2017

Journal of Nuclear Materials

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“…Irradiation-induced Ni–Si nanoclusters or γ’-phase nanoprecipitates have long been known to form in austenitic stainless steels [ 4 , 7 , 26 , 45 , 46 , 47 , 48 , 49 , 50 , 51 , 52 , 53 , 54 ]. Zinkle and colleagues’ 1993 compilation [ 55 ] of irradiation-induced precipitation behaviors in legacy specimens of solution-annealed 316 SS suggests that the γ’ precipitate phase forms within a limited range of temperatures, from 400–500 °C, and doses exceeding ~40 dpa.…”

Section: Discussionmentioning

confidence: 99%

Nanocluster Evolution in D9 Austenitic Steel under Neutron and Proton Irradiation

Mullurkara,

Bejawada,

Sen

et al. 2023

Materials

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Austenitic stainless steel D9 is a candidate for Generation IV nuclear reactor structural materials due to its enhanced irradiation tolerance and high-temperature creep strength compared to conventional 300-series stainless steels. But, like other austenitic steels, D9 is susceptible to irradiation-induced clustering of Ni and Si, the mechanism for which is not well understood. This study utilizes atom probe tomography (APT) to characterize the chemistry and morphology of Ni–Si nanoclusters in D9 following neutron or proton irradiation to doses ranging from 5–9 displacements per atom (dpa) and temperatures ranging from 430–683 °C. Nanoclusters form only after neutron irradiation and exhibit classical coarsening with increasing dose and temperature. The nanoclusters have Ni3Si stoichiometry in a Ni core–Si shell structure. This core–shell structure provides insight into a potentially unique nucleation and growth mechanism—nanocluster cores may nucleate through local, spinodal-like compositional fluctuations in Ni, with subsequent growth driven by rapid Si diffusion. This study underscores how APT can shed light on an unusual irradiation-induced nanocluster nucleation mechanism active in the ubiquitous class of austenitic stainless steels.

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“…A large number of helium atoms generated in (n, α) nuclear reactions will be trapped by defects in materials such as cavities and dislocations, the growth of which will cause a degradation of the mechanical properties through the processes such as embrittlement, swelling, and hardening [3][4][5]. Many studies showed that the interaction of helium and the defects such as dislocation may play an important role in promoting the formation of helium-vacancy complexes or helium bubbles in structural materials [6][7][8][9]. Xu, et al indicated that low-energy helium implantation can cause a decrease of the tensile strength in deformed Fe material [10].…”

Section: Introductionmentioning

confidence: 99%

The effect of dislocation on defects in 316L stainless steel irradiated by helium

Song

Lian

et al. 2023

JJAP Conf. Proc.

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Inhibition of the movement of helium atoms produced by transmutation reactions under nuclear irradiation can be achieved by intentionally introduced trapping sites such as dislocations in stainless steels. In order to investigate the effect of dislocations in 316L stainless steel on helium irradiationinduced defects, well-annealed 316L stainless steel specimens were cold-rolled to either 10 % or 20 % reduction in thickness and then annealed at 723 K for 1 h, respectively. The non-deformed, 10 % and 20 % deformed specimens were irradiated with helium ions at an energy of 5 keV to a dose of 5 × 10 16 ion/cm 2 under ambient temperature. The effects of dislocations on defects generated by helium ion irradiation and helium desorption with temperature were characterized by slow positron beam Doppler broadening spectroscopy and thermal desorption spectroscopy. The results shows that dislocations have a trend to restrict the migration and aggregation of helium atoms and vacancy-type defects, and also hinder the formation of large helium bubbles.

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Evolution of the radiation-induced defect structure in 316 type stainless steel after post-irradiation annealing

Cited by 29 publications

References 29 publications

Annealing effect on microstructural recovery in 316L and A533B

Annealing effect on microstructural recovery in 316L and A533B

Nanocluster Evolution in D9 Austenitic Steel under Neutron and Proton Irradiation

The effect of dislocation on defects in 316L stainless steel irradiated by helium

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