Experimental study on molten corium-concrete interaction with simulant metal and oxide

被引:5
作者
Xu, Zhichun [1 ]
Zhang, Yapei [1 ]
Wu, Zijie [2 ]
Zhan, Dekui [2 ]
Su, G. H. [1 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
[2] China Nucl Power Technol Res Inst Co Ltd, Shenzhen 518000, Peoples R China
基金
国家重点研发计划;
关键词
Severe accident; MCCI; Concrete ablation; Crust anchoring; CINA experiment; CODE;
D O I
10.1016/j.anucene.2021.108767
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
Under hypothetical Reactor Pressure Vessel (RPV) failure accidents in Light Water Reactor (LWR), Molten Corium-Concrete Interaction (MCCI) will cause erosion of cavity concrete, possibly resulting in containment failure due to basemat penetration and overpressure. The CINA (Corium-Concrete Interaction Apparatus) experiment was conducted to investigate the MCCI of metallic and oxidic corium with siliceous concrete. Simulant melt material metallic iron and oxidic alumina generated by exothermic thermite chemical reaction was used to investigate the two-dimensional erosion of a cylindrical crucible in CINA experiment. The crucible was fabricated from siliceous concrete with an inner diameter of 300 mm and a height of 500 mm containing reinforcement (rebars). Decay heat in the melt was simulated by subsequent sustained addition of thermite. During the experiment, the melt temperature was monitored by two thermocouples and a two-color optical endurance pyrometer. Besides, the phenomenon that appeared on the melt surface was recorded by the video camera placed above the crucible and the formation process of the crust anchoring was observed. After the experiment, the crucible was split in half by a wire saw to accurately measure the ablation depth. Axial-radial ablation depths were 25 mm and 13 mm, respectively. Current findings contribute to the further understanding of MCCI mechanisms and the optimization of MCCI mitigation strategies. (c) 2021 Published by Elsevier Ltd.
引用
收藏
页数:8
相关论文
共 28 条
[2]  
Alsmeyer H., 1986, P INT ANS ENS TOP M
[3]  
Blose R., 1993, CORECONCRETE INTERAC
[4]  
Blose R.E., 1987, SWISS: Sustained Heated Metallic Melt/Concrete Interactions with Overlying Water Pools
[5]  
Bonnet J.M., 2017, State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability
[6]  
Bouyer V., 2019, 9 EUR REV M SEV ACC
[7]   Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants [J].
Brissonneau, Laurent ;
Ikeuchi, Hirotomo ;
Piluso, Pascal ;
Gousseau, Josselin ;
David, Cedric ;
Testud, Veronique ;
Roger, Julien ;
Bouyer, Viviane ;
Kitagaki, Toru ;
Nakayoshi, Akira ;
Dubois, Sylvie ;
Washiya, Tadahiro .
JOURNAL OF NUCLEAR MATERIALS, 2020, 528
[8]  
Copus E, 1992, CORE CONCRETE INTERA
[9]   A REVIEW OF THE BETA-EXPERIMENTAL RESULTS AND CODE COMPARISON CALCULATIONS [J].
CORRADINI, M ;
REINEKE, HH .
NUCLEAR SCIENCE AND ENGINEERING, 1989, 102 (03) :260-282
[10]  
Farmer M., 2011, OECD MCCI 2 D CORE C, DOI DOI 10.2172/1014854