Modeling the cracking of cover concrete due to non-uniform corrosion of reinforcement

Du, Xiuli; Jin, Liu; Zhang, Renbo

doi:10.1016/j.corsci.2014.08.025

Cited by 109 publications

(47 citation statements)

References 42 publications

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“…The increase in crack width due to corrosion in specimens with #19 rebar was less compared to those with a #10 rebar. These findings are in line to what has been reported in the literature (Houston et al 1972;Rasheeduzzafar et al 1992;Du et al 2014).…”

Section: Resultssupporting

confidence: 83%

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Attar

Gencturk

Hanifehzadeh

et al. 2016

ACT

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Dry cask storage systems (DCSS) are widely used worldwide for storage of spent nuclear fuel (SNF). Particularly, in the United States, other than the SNF pools, DCSS are the only means for storage of SNF. In the United States, the DCSS are licensed for an initial 20 years (with a possible extension of 40 years). The absence of a long-term (or permanent) storage facility has brought up concerns regarding the long-term performance of DCSS, which may now have to be used for extended durations reaching over 100 years. The DCSS with an exposed concrete overpack account for approximately 61% of the DCSS inventory in the United States. The corrosion of the steel reinforcing bars (rebar) and the alkali-silica reactivity (ASR) of concrete have been identified as two of the main degradation mechanisms. In this paper, the accelerated aging of reinforced concrete (RC) overpacks of a vertical DCSS is evaluated experimentally at the structural scale. Three 1/3-scale specimens were fabricated. The first specimen was built using a conventional selfconsolidating concrete to serve as a control. The second and third specimens were prepared using special concrete mixtures, designed to accelerate the corrosion of rebar and ASR. All three casks were observed for 2 years for aginginduced deterioration using various non-destructive approaches including visual inspection, half-cell potential, Schmidt hammer, and ultra-sonic pulse velocity (UPV) measurements. The RC overpacks have been observed to exhibit significant distress due to these aging mechanisms. The overall conclusion is that accelerating ASR and corrosion through use of reactive aggregates and/or addition of chemicals (NaOH and CaCl 2 in this particular case) is a viable and practical approach for large-scale studies. Although accelerated aging of concrete structures have been extensively studied in the literature, this is one of the first studies on the long-term degradation in DCSS due to corrosion and ASR.

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Section: Resultssupporting

confidence: 83%

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Attar

Gencturk

Hanifehzadeh

et al. 2016

ACT

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Section: Resultssupporting

confidence: 83%

Special Issue: Aging Management of Nuclear Power Plant

Maruyama¹

2016

ACT

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PrefaceEven after the accident of the Fukushima Daiichi Nuclear Power Plant, the Japanese government has positioned nuclear power as an important base load power source in terms of energy policies and has focused on safety operation of the nuclear power generation. This is because it is an indispensable power source for the use of renewable energy in Japan with limited resources. On the other hand, the first generation commercial reactors in the world generally have a designed life of 30 to 40 years, but most of them have been in existence for more than 20 years. Japan is no exception, and several NPPs aged already more than 40 years.Analysis and research show that many commercial reactors leave enough capacity to operate beyond the designed service period. Replacement of the concrete members used in the reactor buildings is expensive making it difficult in many cases. Therefore, in order to continue nuclear power generation over the long term, it is necessary to maintain the performance of the concrete member during the designed service period. From this point of view, it is indispensable to conduct research on maintenance management, performance evaluation, and prediction of deterioration of concrete structures.Research on concrete in the field of civil engineering and building science has been conducted for a long time, while reevaluation of concrete performance, physical properties and various problems in terms of nuclear field needs, i.e. Plant Life Management and Ageing Management, and addressing issues peculiar to the nuclear power field will be an important contribution from the field of concrete research to the field of nuclear power engineering. As discussed at OECD / NEA, alkali silica reactions and radiation influence are important issues for the maintenance of nuclear power plants, and many research on them has been reported.Also in the past, research investment on concrete in the field of nuclear power has been carried out many times in Japan as well as in other developed countries. However, the international publication of the research results has been limited. In this ACT special issue, especially on advanced research in recent years, I widely urged stakeholders to make efforts to allow research trends in Japan to be forecast from other countries.Based on these backgrounds, we applied for papers focusing on Plant Life Management at nuclear power plant facilities and related technologies in the research related to concrete. I think that it became a State of the Art report, which highlights the current problems. I also anticipate it could lead to a trust from the society concerning future nuclear power generation technology and a development of the concrete research field. AbstractA review of the current state of knowledge on the effects of radiation on concrete in nuclear power production applications is presented. Emphasis is placed on the effects of radiation damage, as reflected by changes in engineering properties of concrete, in the evaluation of the long-term operation and for plant life or...

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“…Indeed corrosion and the distribution of corrosion products in corroded rebar do not occur uniformly in practice and non-uniform corrosion around the rebar is commonly found in real situations [18]. The non-uniform corrosion problem has been studied by finite element methods [27][28][29][30][31] or experimental method [32]. However, for the sake of simplicity, the porous zone around the steel bar and the expansive pressure exerted on the surrounding concrete are both assumed to be uniformly distributed in the tangential direction [1,21] in this paper.…”

Section: Stress Initiation Stagementioning

confidence: 99%

A double-cylinder model incorporating confinement effects for the analysis of corrosion-caused cover cracking in reinforced concrete structures

Zhang

2015

Corrosion Science

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A double-cylinder model incorporating confinement effects for the analysis of corrosion-caused cover cracking in reinforced concrete structures, Corros. Sci. (2015), http://dx. a b s t r a c tIn this paper, a double-cylinder model with a consideration of concrete confinement effects is proposed to simulate reinforcement corrosion-caused cover cracking. The analytical model incorporates force equilibrium in both tangential and radial directions as well as volume expansion and deformation compatibility in the steel-rust-concrete interface. Confinement effects outside the cylinders are taken into account by comparing the numerical and available experimental results. Parametric studies are conducted to investigate the variations of the critical volume of consumed steel, critical expansive pressure and time to cover cracking.

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Modeling the cracking of cover concrete due to non-uniform corrosion of reinforcement

Cited by 109 publications

References 42 publications

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Special Issue: Aging Management of Nuclear Power Plant

A double-cylinder model incorporating confinement effects for the analysis of corrosion-caused cover cracking in reinforced concrete structures

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