TY - JOUR
T1 - Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete
AU - Kim, Baek Joong
AU - Yi, Chongku
N1 - Funding 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).
Publisher Copyright:
© 2016
PY - 2017/2/1
Y1 - 2017/2/1
N2 - 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.
AB - 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.
KW - Cracking potential
KW - High strength concrete
KW - Industrial by-product shrinkage
KW - Nuclear power plant
UR - http://www.scopus.com/inward/record.url?scp=85014102484&partnerID=8YFLogxK
U2 - 10.1016/j.net.2016.07.007
DO - 10.1016/j.net.2016.07.007
M3 - Article
AN - SCOPUS:85014102484
SN - 1738-5733
VL - 49
SP - 224
EP - 233
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 1
ER -