“…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%
“…(a) (Remec et al 2013), (b) , (c) , (d) (Gray 1971), (e) (Elleuch et al 1972), (f) (Dubrovskii 1967), (g) (Kontani et al 2010), (Seeberger and Hilsdorf 1982), (i) (McDowall 1971), (j) (Vodák et al 2011), (k) (Łowińska-Kluge and Piszora 2008), (l) (Kelly et al 1969), (m) (Kitsutaka and Matsuzawa 2010), (n) (Oxfall 2013 Gamma flux (kGy/h) 5 to 20 (a,g) 0.02 to 200 (h,i,j,k,l,m) Gamma dose (MGy) 50 to 200 at 80 yr 0.04 to 1.3 Temperature ( o C) <65 (design) 40 to >250 (d,e) Relative Humidity (-) Strong gradient ~0.5 at 50 mm, ~0.7 at 150 mm, >0.9 at 400 mm at 30 yr (n) Empresa Nacional de Residuos Radiactivos, S.A (EN-RESA), the Spanish national company for nuclear waste, took responsibility for decommissioning the station. In 2009, the Consejo de Seguridad Nuclear (CSN), the Spanish Nuclear Safety Council, convened a meeting with national organizations to evaluate the feasibility of obtaining concrete from Zorita to research the effects of high radiation (neutron and gamma) and temperature on concrete structures.…”
Section: Evaluating Service Irradiated Concrete For Plm and To Informmentioning
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.
“…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%
“…(a) (Remec et al 2013), (b) , (c) , (d) (Gray 1971), (e) (Elleuch et al 1972), (f) (Dubrovskii 1967), (g) (Kontani et al 2010), (Seeberger and Hilsdorf 1982), (i) (McDowall 1971), (j) (Vodák et al 2011), (k) (Łowińska-Kluge and Piszora 2008), (l) (Kelly et al 1969), (m) (Kitsutaka and Matsuzawa 2010), (n) (Oxfall 2013 Gamma flux (kGy/h) 5 to 20 (a,g) 0.02 to 200 (h,i,j,k,l,m) Gamma dose (MGy) 50 to 200 at 80 yr 0.04 to 1.3 Temperature ( o C) <65 (design) 40 to >250 (d,e) Relative Humidity (-) Strong gradient ~0.5 at 50 mm, ~0.7 at 150 mm, >0.9 at 400 mm at 30 yr (n) Empresa Nacional de Residuos Radiactivos, S.A (EN-RESA), the Spanish national company for nuclear waste, took responsibility for decommissioning the station. In 2009, the Consejo de Seguridad Nuclear (CSN), the Spanish Nuclear Safety Council, convened a meeting with national organizations to evaluate the feasibility of obtaining concrete from Zorita to research the effects of high radiation (neutron and gamma) and temperature on concrete structures.…”
Section: Evaluating Service Irradiated Concrete For Plm and To Informmentioning
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.
“…In a later study, Vodak et al 9 speculated that in addition to the effect of pore water radiolysis, the presence of micro-cracks due to radiolytic dehydration of the reaction products in the cement favors the ingress of CO 2 into the monolithic material, and its consequent reaction with the hydration products towards formation of calcium carbonates, especially at lower dose rates of radiation over a longer period of exposure. Conversely, higher total doses of gamma radiation, 130 to 836 MGy, were found to reduce the fraction of crystalline reaction The present study investigates the gamma radiation resistance of a slag-based cement matrix with minimal inclusion of PC.…”
Section: Preprint Version Of Accepted Article Please Cite As: N Mobmentioning
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.
“…To increase the attenuation properties, dense concretes are used, with heavy aggregates against X and c rays, and rather light aggregates against fast neutrons [3,4]. In general, if the radiation level is rather low (like in the X-ray chambers of the medical facilities) and the required density is below 3500 kg/m 3 , using heavyand more expensive -concretes should be weighed against using ordinary -and less expensive -concretes, unless the structural problem is controlled by member size.…”
Section: Introductionmentioning
confidence: 99%
“…The decomposition of calcium peroxide leads to the production of calcite by combination with carbon dioxide (carbonation [3,4,19]). Such carbonation occurs in the bulk of the material and is independent from the natural carbonation along the surfaces.…”
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