Degradation mechanisms in overpack concrete of spent nuclear fuel dry storage systems: A review

被引:5
|
作者
Elshazli, Mohamed T. [1 ]
Ibrahim, Ahmed [1 ]
Eidelpes, Elmar [2 ]
Ilevbare, Gabriel O. [3 ]
机构
[1] Univ Idaho, Dept Civil & Environm Engn, Moscow, ID 83844 USA
[2] Idaho Natl Lab, Used Fuel Management Dept, Nucl Sci & Technol, Idaho Falls, ID 83415 USA
[3] Idaho Natl Lab, Mat Sci & Mfg Dept, Energy & Environm Sci & Technol, Idaho Falls, ID 83415 USA
关键词
ALKALI-SILICA REACTION; CHLORIDE-INDUCED CORROSION; BLAST-FURNACE SLAG; FREEZE-THAW RESISTANCE; CARBONATE REACTION ACR; FLY-ASH CONCRETE; FROST-RESISTANCE; PHASE-TRANSITIONS; REINFORCED-CONCRETE; ACTIVATED SLAG;
D O I
10.1016/j.nucengdes.2023.112632
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Dry storage systems are successfully used for interim storage of commercial spent nuclear fuel (SNF). Many of these systems consist of sealed, welded canisters placed inside concrete storage modules. Associated with the need for extending the operational periods of some of these systems, there are concerns that their concrete overpacks could degrade over time. This could lead to a loss of strength and durability. Potential degradation mechanisms include chemical attacks, concrete cancer, or freeze-thaw (F-T) cycles, making them prone to failure during extended periods of dry storage, especially when stressed during a hazardous event, such as an earthquake. The concrete mixtures that have been used in dry storage systems have not changed significantly since their introduction, and available mixtures often have the same ingredients used in conventional concrete. With the latest evolutions in material science, new concrete composites with ultra-high strength and outstanding thermal and mechanical properties can be utilized in such structures. Within a collaboration between the University of Idaho and the Idaho National Laboratory, enabled by funding provided by the Center of Advanced Energy Systems (CAES), a thorough review of SNF dry storage system overpack degradation observations were conducted. Further, the latest technologies in concrete composite materials with extraordinary strength, outstanding durability were identified. This paper presents and summarizes the most relevant mechanism of concrete deterioration in SNF systems, and identifies new materials to be used in future concrete mixtures to increase the service life of SNF dry storage systems and to lengthen inspection intervals.
引用
收藏
页数:19
相关论文
共 50 条
  • [21] Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond
    Wiss, Thierry
    Hiernaut, Jean-Pol
    Roudil, Daniele
    Colle, Jean-Yves
    Maugeri, Emilio
    Talip, Zeynep
    Janssen, Arne
    Rondinella, Vincenzo
    Konings, Rudy J. M.
    Matzke, Hans-Joachim
    Weber, William J.
    JOURNAL OF NUCLEAR MATERIALS, 2014, 451 (1-3) : 198 - 206
  • [22] Spent nuclear fuel storage
    不详
    CHEMISTRY WORLD, 2011, 8 (06): : 5 - 5
  • [23] Spent nuclear fuel in dry storage conditions - current trends in fuel performance modeling
    Konarski, Piotr
    Cozzo, Cedric
    Khvostov, Grigori
    Ferroukhi, Hakim
    JOURNAL OF NUCLEAR MATERIALS, 2021, 555
  • [24] Spent fuel dry storage in Hungary
    Takáts, F
    Buday, G
    STORAGE OF SPENT FUEL FROM POWER REACTORS, 2003, 20 : 25 - 29
  • [25] Evolution of Spent Fuel Dry Storage
    Standring, Paul Nicholas
    Takats, Ferenc
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2016, 61 (11): : 673 - 678
  • [26] DRY STORAGE OF DIORIT SPENT FUEL
    OSPINA, C
    ATOMWIRTSCHAFT-ATOMTECHNIK, 1983, 28 (11): : 569 - 570
  • [27] DRY CASK STORAGE OF SPENT FUEL
    ARITOMI, M
    AOKI, S
    SAEGUSA, T
    KAWASAKI, R
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1989, 31 (03): : 331 - 346
  • [28] MODULAR DRY STORAGE OF SPENT FUEL
    BAXTER, JW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 130 - 131
  • [29] Topics of research and development on concrete cask storage of spent nuclear fuel
    Saegusa, Toshiari
    Yagawa, Genki
    Aritomi, Masanori
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (05) : 1168 - 1174
  • [30] Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review
    El-Samrah, Moamen G.
    Tawfic, A. F.
    Chidiac, Samir E.
    ANNALS OF NUCLEAR ENERGY, 2021, 160