HECLA experiments on interaction between metallic melt and hematite-containing concrete

Sevón, Tuomo; Kinnunen, Tuomo; Virta, Jouko; Holmström, Stefan; Kekki, Tommi; Lindholm, Ilona

doi:10.1016/j.nucengdes.2010.04.039

Cited by 33 publications

(13 citation statements)

References 5 publications

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“…Therefore, the sacrificial concrete in the EPR reactor is a special type "FeSi" concrete, which includes both high density aggregates, hematite (Fe 2 O 3 ) and siliceous (SiO 2 ). And the density of sacrificial concrete used in EPR is around 2600 kg/m 3 (Sevón et al 2010). High density aggregate prone to sinking in fresh mortar and induced dry shrinkage in the surface layer of sacrificial concrete.…”

Section: Resultsmentioning

confidence: 99%

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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Section: Resultsmentioning

confidence: 99%

Special Issue: Aging Management of Nuclear Power Plant

Maruyama¹

2016

ACT

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“…Another important parameter that affects sacrificial concrete ablation is the temperature at MCCI, which is defined as the ablation temperature of sacrificial concrete in MELCOR. The ablation temperature of ferrosiliceous sacrificial concrete used in the study is 1453 K, according to [1].…”

Section: Main Assumptions For the Calculationmentioning

confidence: 99%

“…As aforementioned, the sacrificial concrete is critical to the core catcher in EPR pit. It mainly contains Fe 2 O 3 and SiO 2 with the total content reaching 76.7% [1,2]. Previous studies indicated that heat released from the interactions of Fe 2 O 3 and SiO 2 with zirconium accounts for the ablation of concrete [17].…”

Section: Fe 2 O 3 Contentmentioning

confidence: 99%

“…In a simulated core melt accident of nuclear power plant (NPP), a molten pool called corium can melt through the reactor pressure vessel (RPV) and be released to the containment basemat. Driven by the decay power of the fission products and the high temperature, the basemat concrete, which is the last barrier that prevents leakage of the radioactive products into environment in the secondgeneration NPPs, starts to ablate [1,2]. Thus, the molten coreconcrete interaction (MCCI) is of great importance in NPP because it may result in leakage of fission products.…”

Section: Introductionmentioning

confidence: 99%

“…Thus, the molten coreconcrete interaction (MCCI) is of great importance in NPP because it may result in leakage of fission products. Previous studies show that the concrete properties have significant impact on MCCI [1][2][3][4][5][6]. In the third-generation NPPs, such as European Pressurized Water Reactor (EPR) [7], a core catcher is introduced to encase the corium, through which the integrity of the containment is preserved.…”

Section: Introductionmentioning

confidence: 99%

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Influence of Concrete Properties on Molten Core-Concrete Interaction: A Simulation Study

Jiang

Chu

et al. 2016

Advances in Materials Science and Engineering

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In a severe nuclear power plant accident, the molten core can be released into the reactor pit and interact with sacrificial concrete. In this paper, a simulation study is presented that aims to address the influence of sacrificial concrete properties on molten core-concrete interaction (MCCI). In particular, based on the MELCOR Code, the ferrosiliceous concrete used in European Pressurized Water Reactor (EPR) is taken into account with respect to the different ablation enthalpy and Fe2O3 and H2O contents. Results indicate that the concrete ablation rate as well as the hydrogen generation rate depends much on the concrete ablation enthalpy and Fe2O3 and H2O contents. In practice, the ablation enthalpy of sacrificial concrete is the higher the better, while the Fe2O3 and H2O content of sacrificial concrete is the lower the better.

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