Meso-scale modeling of irradiated concrete in test reactor

Giorla, Alain B.; Vaitová, Michaela; Pape, Yann Le; Štemberk, Petr

doi:10.1016/j.nucengdes.2015.08.027

Cited by 44 publications

(42 citation statements)

References 58 publications

(61 reference statements)

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“…Due to aggregate expansion, the mortar matrix in concrete is damaged, resulting in deterioration of concrete's physical properties, such as compressive strength and Young's modulus, such as in the case of alkali-silica reaction in concrete (Giorla et al 2015;.…”

Section: Introductionmentioning

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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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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Section: Introductionmentioning

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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“…The main reason is considered as an expansion of aggregate, because α-quartz is well-known to show an expansion and density reduction under neutron and electron irradiation (Primak et al 1955;Primak 1958;Bonnet et al 1994;Douillard and Duraud 1996;Bolse 1999;Ewing et al 2000;Field et al 2015). It is hence considered that the natural rock should be sensitive to irradiation, which poses very important issues on the durability of concrete under irradiation as 1) expansion of aggregate, and 2) degradation of concrete performance as a result of 1) (Maruyama et al 2012;Field et al 2015;Giorla et al 2015;Le Pape et al 2015Maruyama et al 2016).…”

Section: Introductionmentioning

confidence: 99%

Change in Relative Density of Natural Rock Minerals Due to Electron Irradiation

Maruyama

Muto

2016

ACT

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We investigated changes in the density of natural rock minerals following high-energy electron irradiation, using the plasmon peak shift of electron energy-loss spectra and transmission electron microscopy. The target materials were the natural rock minerals α-quartz, orthoclase, anorthite, albite, biotite, muscovite, and chlorite. These crystalline minerals can be classified into three groups based on their Si-network geometries: 3-dimensional 6-member ring; 4-member ring + 6-member ring; and planar 6-member ring. The metamictization rates and changes in relative density are discussed using a phenomenological model, which we used to identify the physical parameters that describe the metamictization process as a function of the volume density of Si and Al atoms, or Si atoms alone, in the crystal structures. The relative densities following metamictization all decreased by more than a few percent, except for albite, which became denser. These results suggest that radiolysis damage causes initial compaction, then metamictization, characterized by the expansion of the Siand Al-polyhedra in the aggregate. The stability of concrete containing α-quartz, orthoclase, and anorthite should be further investigated in the light of the present results.

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“…A 2D mesoscale model for irradiated concrete (Giorla, Vaitová et al 2015) was developed at ORNL based on the AMIE finite element framework (Dunant and Scrivener 2010, Giorla et al 2014). The model aim is to provide the concrete expansion and internal degradation as a function of the aggregate RIVE and the mechanical properties of the paste and the aggregates, notably accounting for the coupling between creep and damage in the cement paste (Giorla, Le Pape and Dunant 2016).…”

Section: Numerical Models Mesoscale Modelmentioning

confidence: 99%

“…Limited irradiated concrete structural analyses have been published in the open literature using different models: analytical axisymmetric models (Andreev and Kapliy 2014;Le Pape 2015), finite-element membrane models (Mirhosseini et al 2014), finite-element contin- Fig. 4 Comparison of calculated concrete RIVE with experimental data from Elleuch et al (1972), and example of simulated damage pattern at a neutron fluence of 1.3×10…”

Section: Summary Of Concrete Structural Analysis Literaturementioning

confidence: 99%

“…In the absence of RIVE (or swelling), radiation damage [i.e., induced loss of mechanical properties (Hilsdorf et al 1978;Field et al 2015)] has very limited effects on the CBS (Pomaro et al 2011). Moreover, the radiation field's strong attenuation produces a high RIVE gradient (Le Pape 2015) causing high biaxial compressive elastic stresses in the vertical and hoop directions near the reactor cavity and important tensile hoop stresses toward the back of the CBS (Andreev and Kapliy 2014;Le Pape 2015). Simultaneously, the prolonged moderate temperature exposure (<65°C by design) and strong internal moisture content gradient (Oxfall 2013) affect the degree of hydration of concrete, and thus, its mechanical properties.…”

Section: Summary Of Concrete Structural Analysis Literaturementioning

confidence: 99%

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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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Meso-scale modeling of irradiated concrete in test reactor

Cited by 44 publications

References 58 publications

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

Change in Relative Density of Natural Rock Minerals Due to Electron Irradiation

Special Issue: Aging Management of Nuclear Power Plant

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