In Korea, attempts have been made to develop high strength concrete for the safety and design life improvement of nuclear power plants. In this study, the cracking potentials of nuclear power plant-high strength concretes (NPP-HSCs) containing industrial by-products with W/B 0.34 and W/B 0.28, which are being reviewed for their application in the construction of containment structures, were evaluated through autogenous shrinkage, unrestrained drying shrinkage, and restrained drying shrinkage experiments. The cracking potentials of the NPP-HSCs with W/B 0.34 and W/B 0.28 were in the order of 0.34FA25 > 0.34FA25BFS25 > 0.34BFS50 > 0.34BFS65SF5 and 0.28FA25SF5 >> 0.28BFS65SF5 > 0.28BFS45SF5 > 0.28 FA20BFS25SF5, respectively. The cracking potentials of the seven mix proportions excluding 0.28FA25SF5 were lower than that of the existing nuclear power plant concrete; thus, the durability of a nuclear power plant against shrinkage cracking could be improved by applying the seven mix proportions with low cracking potentials.
Bibliographical noteFunding Information:
This research was supported by the Nuclear Power R&D Program of the Korea Institute of Energy Technology Evaluation and Planning (Seoul, Korea), by a grant funded by the Korea Government Ministry of Knowledge Economy (Grant No., 2011T100200161), and by the Basic Science Research Program through the National Research Foundation of Korea (NRF) funded by the Ministry of Education, Science and Technology (Sejong, Korea; Grant No., NRF-2013R1A1A2012788). In addition, this study was supported in part by a grant from the Korea University (Seoul, Korea).
- Cracking potential
- High strength concrete
- Industrial by-product shrinkage
- Nuclear power plant
ASJC Scopus subject areas
- Nuclear Energy and Engineering