Effect of Cr coating on the mechanical integrity of Accident Tolerant Fuel cladding under ring compression test

被引:8
|
作者
Kim, Jinsu [1 ]
Joung, SungHoon [2 ]
Lee, Youho [2 ]
机构
[1] Seoul Natl Univ, Nucl Res Inst Future Technol & Policy, 1 Gwanak Ro, Seoul 08826, South Korea
[2] Seoul Natl Univ, Dept Nucl Engn, 1 Gwanak Ro, Seoul 08826, South Korea
关键词
Accident tolerant fuel (ATF); Cr-coated cladding; Ring compression test (RCT); Finite element analysis (FEA); Mechanical integrity; HIGH-TEMPERATURE OXIDATION; LATERAL COMPRESSION; COATED ZIRCALOY-4; BEHAVIOR; HYDRIDE; TUBE; EMBRITTLEMENT; SIMULATION; FRACTURE;
D O I
10.1016/j.jnucmat.2023.154603
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The mechanical behavior of Cr-coated Zr-Nb alloy cladding was investigated with Ring Compression Test (RCT) and Finite Element Analysis (FEA). The post-RCT specimens were examined by SEM analysis with a focus on crack characterization. The experimental result shows that Cr-coating less than 20 & mu;m does not introduce notable changes in the load-displacement behavior of the cladding structure until the point at which the Cr-coated cladding undergoes premature failure. FEA results demonstrate that the premature failure of the Cr-coated cladding cannot be explained by local stress and strain fields as they are not affected by the presence of the coating if the crack of the coating layer is not considered. Under RCT, a crack is initially formed across the coating thickness and acts as a pre-existing flaw that concentrates stresses, growing towards the underlying Zr-Nb alloy. Once the crack depth attains the critical size, it unstably grows, resulting in cladding failure which is shown as an earlier load drop compared to the uncoated cladding. FEA results using eXtended Finite Element Method (XFEM) demonstrate the stress concentration by the coating crack which results in the premature failure of the Cr-coated cladding in RCT. Increasing coating thickness decreases crack density, thereby reducing the uncovered area of the underlying cladding in case where the coating experiences extended cracking. On the other hand, the thicker coating, when cracked, can induce extended damage to the underlying cladding by introducing larger cracks. The net benefit of these two competing effects needs to be considered to optimize the thickness of Cr-coating.
引用
收藏
页数:14
相关论文
共 50 条
  • [21] Study on Process and Properties of Pulse Laser Prepared Cr Coating for Accident Tolerant Fuel Claddings
    Li R.
    Liu T.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (01): : 74 - 77
  • [22] Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel
    Reed, Brady
    Wang, Rick
    Lu, Roger Y.
    Qu, Jun
    WEAR, 2021, 466
  • [23] A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding
    Cinbiz, M. Nedim
    Brown, Nicholas R.
    Terrani, Kurt A.
    Lowden, Rick R.
    Erdman, Donald, III
    ANNALS OF NUCLEAR ENERGY, 2017, 109 : 396 - 404
  • [24] Study on thermal performance of accident tolerant fuel with UO2 mixed pellet and zircaloy cladding coating
    Chen, Ping
    Liu, Zhenhai
    Li, Wenjie
    Xing, Shuo
    Hedongli Gongcheng/Nuclear Power Engineering, 2015, 36 : 84 - 86
  • [25] Preparation, structure, and properties of an AlCrMoNbZr high-entropy alloy coating for accident-tolerant fuel cladding
    Zhang, W.
    Tang, R.
    Yang, Z. B.
    Liu, C. H.
    Chang, H.
    Yang, J. J.
    Liao, J. L.
    Yang, Y. Y.
    Liu, N.
    SURFACE & COATINGS TECHNOLOGY, 2018, 347 : 13 - 19
  • [26] Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material
    Umretiya, Rajnikant V.
    Vargas, Santiago
    Galeano, Diana
    Mohammadi, Reza
    Castano, Carlos E.
    Rojas, Jessika V.
    JOURNAL OF NUCLEAR MATERIALS, 2020, 535
  • [27] Intrinsic effects of Cr-layered accident-tolerant fuel cladding surface on reflood heat transfer
    Shin, Doyoung
    Kim, Sung Joong
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2022, 186
  • [28] Diffusion of chromium of Cr-coated Zircaloy accident tolerant fuel cladding: Model development and experimental validation
    Kim, Dongju
    Lee, Youho
    SURFACE & COATINGS TECHNOLOGY, 2023, 468
  • [29] Effect of chromium coated zircaloy cladding of accident tolerant fuel on the best estimate LOCA methodology
    Bae, Jae -Ho
    Hong, Soon-Joon
    Ro, Tae -Sun
    PROGRESS IN NUCLEAR ENERGY, 2022, 151
  • [30] Quenching experiment on Cr-alloy-coated cladding for accident-tolerant fuel in water pool under low and high subcooling conditions
    Lee, Kwan-Geun
    In, Wang-Kee
    Kim, Hyun-Gil
    NUCLEAR ENGINEERING AND DESIGN, 2019, 347 : 10 - 19