Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete

Baek Joong Kim; Chongku Yi

doi:10.1016/j.net.2016.07.007

Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete

Baek Joong Kim, Chongku Yi

Research output: Contribution to journal › Article › peer-review

8 Citations (Scopus)

Abstract

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.

Original language	English
Pages (from-to)	224-233
Number of pages	10
Journal	Nuclear Engineering and Technology
Volume	49
Issue number	1
DOIs	https://doi.org/10.1016/j.net.2016.07.007
Publication status	Published - 2017 Feb 1

Bibliographical note

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

Keywords

Cracking potential
High strength concrete
Industrial by-product shrinkage
Nuclear power plant

ASJC Scopus subject areas

Nuclear Energy and Engineering

Access to Document

10.1016/j.net.2016.07.007

Cite this

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title = "Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete",

abstract = "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.",

keywords = "Cracking potential, High strength concrete, Industrial by-product shrinkage, Nuclear power plant",

author = "Kim, {Baek Joong} and Chongku Yi",

note = "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: {\textcopyright} 2016",

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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.

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Experimental Study on the Shrinkage Properties and Cracking Potential of High Strength Concrete Containing Industrial By-Products for Nuclear Power Plant Concrete

Abstract

Bibliographical note

Keywords

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