Feasibility of UHPC shields in spent fuel vertical concrete cask to resist accidental drop impact

被引:5
|
作者
Jia, P. C. [1 ]
Wu, H. [1 ]
Ma, L. L. [1 ]
Peng, Q. [1 ]
机构
[1] Tongji Univ, Coll Civil Engn, Shanghai 200092, Peoples R China
基金
中国国家自然科学基金;
关键词
Ultra -high performance concrete; Vertical concrete cask; Numerical simulation; Accidental drop; Optimal design; REINFORCED-CONCRETE; STORAGE; PERFORMANCE;
D O I
10.1016/j.net.2022.07.012
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
Ultra-high performance concrete (UHPC) has been widely utilized in military and civil protective structures to resist intensive loadings attributed to its excellent properties, e.g., high tensile/compressive strength, high dynamic toughness and impact resistance. At present, aiming to improve the defects of the traditional vertical concrete cask (VCC), i.e., the external storage facility of spent fuel, with normal strength concrete (NSC) shield, e.g., heavy weight and difficult to fabricate/transform, the feasibility of UHPC applied in the shield of VCC is numerically examined considering its high radiation and corrosion resistance. Firstly, the finite element (FE) analyses approach and material model parameters of NSC and UHPC are verified based on the 1/3 scaled VCC tip-over test and drop hammer test on UHPC members, respectively. Then, the refined FE model of prototypical VCC is established and utilized to examine its dynamic behaviors and damage distribution in accidental tip-over and end-drop events, in which the various influential factors, e.g., UHPC shield thickness, concrete ground thickness, and sealing methods of steel container are considered. In conclusion, by quantitatively evaluating the safety of VCC in terms of the shield damage and vibrations, it is found that adopting the 300 mm-thick UHPC shield instead of the conventional 650 mm-thick NSC shield can reduce about 1/3 of the total weight of VCC, i.e., about 50 t, and 37% floor space, as well as guarantee the structural integrity of VCC during the accidental drop simultaneously. Besides, based on the parametric analyses, the thickness of concrete ground in the VCC storage site is recommended as less than 500 mm, and the welded connection is recommended for the sealing method of steel containers.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:4146 / 4158
页数:13
相关论文
共 44 条
  • [41] Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions
    Almomani, Belal
    Kim, Seyeon
    Jang, Dongchan
    Lee, Sanghoon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (05) : 1079 - 1092
  • [42] Initiation and Propagation of Stress Corrosion Cracking of Stainless Steel Canister for Concrete Cask Storage of Spent Nuclear Fuel (Reprinted from Proceedings of the CORROSiON/2008 Research Topical Symposium)
    Tani, J. -I.
    Mayuzurmi, M.
    Hara, N.
    CORROSION, 2009, 65 (03) : 187 - 194
  • [43] Structural integrity of a high-burnup spent fuel rod under drop impact considering pellet-clad interfacial bonding influence
    Almomani, Belal
    Jang, Dongchan
    Lee, Sanghoon
    NUCLEAR ENGINEERING AND DESIGN, 2018, 337 : 324 - 340
  • [44] ANALYTICAL AND NUMERICAL EVALUATION OF THE IMPACT LIMITERS DESIGN OF A RESEARCH REACTORS SPENT FUEL TRANSPORTATION PACKAGE HALF SCALE MODEL UNDER 9 M DROP TESTS
    Neto, Miguel Mattar
    Miranda, Carlos A. J.
    Fainer, Gerson
    Mourao, Rogerio P.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7, 2009, : 245 - 250