Effect of γ-irradiation on strength of concrete for nuclear-safety structures

Vodák, F.; Trtík, K.; Sopko, V.; Kapičková, O.; Demo, P.

doi:10.1016/j.cemconres.2004.10.016

Cited by 69 publications

(36 citation statements)

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“…The existing data (Vodák et al 2005) also support this assumption. Production of calcium peroxide octahydrate must be related to the portlandite and water content in the cement paste.…”

Section: 2supporting

confidence: 54%

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A Numerical Model for Concrete Strength Change under Neutron and Gamma-ray Irradiation

Maruyama

Haba²,

Sato

et al. 2016

ACT

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For performance evaluation of existing reinforced concrete members under irradiation conditions, a numerical code called "DEVICE" (Damage EValuation for Irradiated ConcretE), which takes into account the heat, moisture, and radiation transport coupled with cement hydration, is proposed. This code is composed of the established computational cement-based material (CCBM) model and the one-dimensional deterministic transport Sn code "ANISN". In the proposed model, temperature-dependent irradiation-induced expansion of aggregate minerals and resultant strength deterioration of concrete are introduced. Currently, the knowledge and modeling of irradiation-induced expansion of aggregate mineral is limited only for α-quartz. DEVICE was used for evaluating the strength distribution of the decommissioned plant Japan Power Demonstration Reactor (JPDR). Compressive strength distribution in a concrete biological shielding (CBS) wall of the JPDR was obtained by core sampling, and the compressive loading test results were compared with the calculation results. This comparison proved the practicality potential of DEVICE to predict the concrete strength distribution in a CBS. In addition, concrete strength change and its distribution in a CBS of an anonymous two-loop pressurized water reactor was simulated by DEVICE. The contributing factors for the change in the distribution of concrete strength at the inner surface of the CBS are discussed. Furthermore, the ways of integrity evaluation other than the existing allowable fast neutron fluence method are proposed and discussed as follows: 1) mineral composition-based allowable fast neutron fluence; 2) strength prediction at the inner surface based on the expansion of mineral composition of aggregates and the lower limit curve of the ratio of compressive strength of the specimen after irradiation (Fc) to that of the reference specimen (Fco) as a function of concrete expansion; and 3) direct numerical calculation for seismic performance by considering irradiation-induced volume expansion and degradation of concrete.

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“…The existing data (Vodák et al 2005) also support this assumption. Production of calcium peroxide octahydrate must be related to the portlandite and water content in the cement paste.…”

Section: 2supporting

confidence: 54%

“…Metastable calcium peroxide octahydrates can be produced in hardened cement paste with high water content (Bouniol and Aspart 1998;Vodák et al 2005;Lowinska-Kluge and Piszora 2008), altering the strength and pore size distribution and especially resulting in subsequent carbonation.…”

Section: 2mentioning

confidence: 99%

A Numerical Model for Concrete Strength Change under Neutron and Gamma-ray Irradiation

Maruyama

Haba²,

Sato

et al. 2016

ACT

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“…This can then favor calcite (CaCO 3 ) formation in the grout. Consistent with this, Vodak et al 7 observed increased calcite formation in aged concrete samples exposed to high doses of gamma radiation, up to 1 MGy over 83 days. They also noted reductions in mechanical strength and pore volume.…”

Section: Preprint Version Of Accepted Article Please Cite As: N Mobsupporting

confidence: 64%

Gamma irradiation resistance of an early age slag-blended cement matrix for nuclear waste encapsulation

et al. 2015

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Irradiation is one of the characteristic conditions that nuclear wasteforms must withstand to assure integrity during their service life. This study investigates gamma irradiation resistance of an early age slag cement-based grout, which is of interest for the nuclear industry as it is internationally used for encapsulation of low and intermediate level radioactive wastes. The slag cement-based grout withstands a gamma irradiation dose of 4.77 MGy over 256 hours without reduction in its compressive strength; however, some cracking of irradiated samples was identified. The high strength retention is associated with the fact that the main hydration product forming in this binder, a calcium aluminum silicate hydrate (C-A-S-H) type gel, remains unmodified upon irradiation. Comparison with a heat-treated sample was carried out to identify potential effects of the temperature rise during irradiation exposure. The results suggested that formation of cracks is a combined effect of radiolysis and heating upon irradiation exposure.

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“…Metastable calcium peroxide octahydrates can be produced in HCP with high water content (Bouniol and Aspart 1998;Vodák et al 2005;Lowinska-Kluge and Piszora 2008), altering the strength and pore size distribution and, especially, resulting in subsequent carbonation. It is also suggested that gamma radiation-induced carbonation increases the strength of HCP (Vodák et al 2005;Vodák et al 2011). Underlying these phenomena is the radiolysis of water.…”

Section: Radiolysis Effectsmentioning

confidence: 99%

Review of the Current State of Knowledge on the Effects of Radiation on Concrete

Rosseel

Maruyama

Pape

et al. 2016

ACT

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A 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 aging management of nuclear power plants (NPPs) in Japan, Spain, and the United States. National issues and concerns are described for Japan and the United States followed by a discussion of the fundamental understanding of the effects of radiation on concrete. Specifically, the effects of temperature, moisture content, and irradiation on ordinary Portland cement paste and the role of temperature and neutron energy spectra on radiation-induced volumetric expansion (RIVE) of aggregate-forming minerals are described. This is followed by a discussion of the bounding conditions for extended operation; the significance of accelerated irradiation conditions; the role of temperature and creep; and how these issues are being incorporated into numerical and meso-scale models. From these insights on radiation damage, analyses of these effects on concrete structures are reviewed, and the current status of work in Japan and the United States is described. Also discussed is the recent formation of a new international scientific and technical organization, the International Committee on Irradiated Concrete, to provide a forum for timely information exchanges among organizations pursuing the identification, quantification, and modeling of the effects of radiation on concrete in commercial nuclear applications. The paper concludes with a discussion of research gaps, including (1) interpreting test-reactor data, (2) evaluating service-irradiated concrete for aging management and to inform radiation damage models with the Zorita NPP (Spain) serving as the first comprehensive test case, (3) irradiated-assisted alkali-silica reactions, and (4) RIVE under constrained conditions.

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Effect of γ-irradiation on strength of concrete for nuclear-safety structures

Cited by 69 publications

References 1 publication

A Numerical Model for Concrete Strength Change under Neutron and Gamma-ray Irradiation

A Numerical Model for Concrete Strength Change under Neutron and Gamma-ray Irradiation

Gamma irradiation resistance of an early age slag-blended cement matrix for nuclear waste encapsulation

Review of the Current State of Knowledge on the Effects of Radiation on Concrete

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