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Cracks in concrete containment - Comparing the self-healing potential under variable air and steam loads between real scale and laboratory scale

Zemann, Moritz; Herrmann, Nico; Willers, Kerstin; Gerlach, Lutz; Müller, H.

Abstract (englisch):
The leak tightness of nuclear power plant containments under accidental conditions is a crucial topic in the safety discussion about the operating lives of nuclear power plants. The self-healing potential of cracks in concrete thereby might contribute an important share to avoid possible contamination of the environment. Small scale flow-through experimetns with air and steam, conducted under variable pressure and temperature conditions at the MPA Karlsruhe shall gap the bridge between previously performed large scale leakage tests and the sole description of the relevant and already well known chemical and physical processes. The tests were conducted on specimens of cementitious constructions materials, i.e. concrete and typical concrete ingredients (sandstone, limestone, granite) to separate possible effects by the material. Experimental conditions were chosen according to realistic temperature and pressure conditions of an accidental scenario. The experimental setup shall first of all measure the amount of flow through the crack and subsequently its reduction accompanying the different crack healing processes. For the assessment ... mehr


Zugehörige Institution(en) am KIT Institut für Massivbau und Baustofftechnologie (IMB)
Publikationstyp Proceedingsbeitrag
Jahr 2017
Sprache Englisch
Identifikator KITopen ID: 1000080666
Erschienen in 24nd Conference on Structural Mechanics in Reactor Technology, Busan, South Korea, August 20 - August 25, 2017
Schlagworte Cracks in concrete containment - Comparing the self-healing potential under variable air and steam loads between real scale and laboratory scale
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