Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

Naus, D.J.

doi:10.2172/931451

Cited by 30 publications

(30 citation statements)

References 53 publications

(18 reference statements)

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“…Degradation induced by radiation includes radiation damage as well as other mechanical and chemical processes triggered by radiation. [Naus, 2007].…”

Section: Introductionmentioning

confidence: 99%

Material degradation due to moisture and temperature. Part 1: mathematical model, analysis, and analytical solutions

Mudunuru

Nakshatrala

2016

Continuum Mech. Thermodyn.

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“…Degradation induced by radiation includes radiation damage as well as other mechanical and chemical processes triggered by radiation. [Naus, 2007].…”

Section: Introductionmentioning

confidence: 99%

Material degradation due to moisture and temperature. Part 1: mathematical model, analysis, and analytical solutions

Mudunuru

Nakshatrala

2016

Continuum Mech. Thermodyn.

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“…These mechanisms affect the concrete, the steel and the interface properties, and reduce structural performance under mechanical loading such as impact. IAEA (1998) and Naus (2007) address potential aging mechanisms, age-related degradation, and aging management for the concrete containment structures for NPPs, which can be extended to DCSS. The degradation factors and their effects are shown in Table 2 (IAEA 1998;Naus 2007).…”

Section: Introductionmentioning

confidence: 99%

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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“…The construction of the reactor containment buildings varies considerably depending on plant type, containment design, and plant vintage. [1][2][3] Containment designs used by all BWR and PWR plants are summarized in Table 1. Of the 104 currently operating plants, 11 BWRs and 55 PWR's are of interest in this paper.…”

Section: Introductionmentioning

confidence: 99%

Containment Liner Corrosion

Dunn

Pulvirenti

Klein

2012

15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems‐Water Reactors

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Of the 104 currently operating nuclear power plants in the U.S, there are 66 plants that have containment buildings constructed with an inner steel liner plate in contact with a thick concrete shell. The steel liner is nominally 6 to 10 mm [0.25 to 0.375 in] thick and is designed in conjunction with the concrete containment building to function as an essentially leak tight barrier against the release of radiation under accident conditions. Corrosion of the containment liner has been observed and corrosion penetration of the liner associated with foreign materials embedded in the concrete from original construction has occurred in a few U.S. plants. This paper reviews plant operating experience, evaluates factors that can affect containment liner corrosion susceptibility, and discusses the mechanisms for through-wall corrosion initiated at the concrete/liner interface.

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Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

Cited by 30 publications

References 53 publications

Material degradation due to moisture and temperature. Part 1: mathematical model, analysis, and analytical solutions

Material degradation due to moisture and temperature. Part 1: mathematical model, analysis, and analytical solutions

Accelerated Aging of Concrete Dry Cask Storage Systems for Nuclear Waste

Containment Liner Corrosion

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