Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding

被引:14
作者
Qi, Feipeng [1 ]
Liu, Zhenhai [1 ]
Li, Quan [1 ]
Yu, Hongxing [1 ]
Chen, Ping [1 ]
Li, Yuanming [1 ]
Zhou, Yi [1 ]
Ma, Chao [1 ]
Tang, Changbing [1 ]
Huang, Yongzhong [1 ]
Zhao, Bo [1 ]
Lu, Huaiyu [1 ]
机构
[1] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610041, Peoples R China
基金
中国国家自然科学基金;
关键词
Accident tolerant fuel (ATF); Cr coating; Pellet-cladding mechanical interaction (PCMI); Power ramp; Thermal-mechanical response; ABAQUS; FUEL PERFORMANCE; OXIDATION BEHAVIOR; CHROMIUM;
D O I
10.1016/j.nucengdes.2020.110792
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
The thermal-mechanical response of Cr-coated Zr cladding during power ramp condition is of critical importance for a better understanding of its reliability and security in ATF designing. The pellet-cladding mechanical interaction (PCMI) performance of Cr-coated Zircaloy cladding was analyzed in this study using multistep modeling strategy to capture the base-irradiation conditions of full-length fuel and the local transient PCMI responses during power ramp conditions. The traditional 1.5D fuel performance code, COPERNIC, and the commercial finite element (FE) code, ABAQUS, were combined to effectively reduce the computational demands while ensuring accuracy of local PCMI prediction. ABAQUS has been enhanced to support thermal, mechanical and irradiation behavior modeling of the coated cladding by adding a set of models representing fuel, cladding and coating in-pile behaviors using user-subroutines. Then, the PCMI responses of three Cr-coated claddings were analyzed under both steady and power ramp conditions. Parametric studies were carried out to demonstrate the effects of several key factors, such as coating thickness, burn-up level and transient power increment, etc., on PCMI behavior of the Cr-coated cladding, which may provide fuel designers and engineers a deeper understanding in thermal-mechanical responses of the Cr-coated cladding.
引用
收藏
页数:11
相关论文
共 25 条
  • [1] Adamson R., 2006, ZIRAT11
  • [2] AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding
    Bischoff, Jeremy
    Delafoy, Christine
    Vauglin, Christine
    Barberis, Pierre
    Roubeyrie, Cedric
    Perche, Delphine
    Duthoo, Dominique
    Schuster, Frederic
    Brachet, Jean-Christophe
    Schweitzer, Elmar W.
    Nimishakavi, Kiran
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (02) : 223 - 228
  • [3] Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
    Brachet, Jean-Christophe
    Idarraga-Trujillo, Isabel
    Le Flem, Marion
    Le Saux, Matthieu
    Vandenberghe, Valerie
    Urvoy, Stephane
    Rouesne, Elodie
    Guilbert, Thomas
    Toffolon-Masclet, Caroline
    Tupin, Marc
    Phalippou, Christian
    Lomello, Fernando
    Schuster, Frederic
    Billard, Alain
    Velisa, Gihan
    Ducros, Cedric
    Sanchette, Frederic
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 517 : 268 - 285
  • [4] PCI analysis of Zircaloy coated clad under LWR steady state and reactor startup operations using BISON fuel performance code
    Capps, Nathan
    Mai, Anh
    Kennard, Michael
    Liu, Wenfeng
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 332 : 383 - 391
  • [5] Dassault Systemes, 2014, ABAQUS
  • [6] Hagrman D.L., 1979, No. NUREG/CR-0497
  • [7] TREE-1280), DOI [10.2172/6442256, DOI 10.2172/6442256]
  • [8] Mechanical and thermomechanical properties of commercially pure chromium and chromium alloys
    Holzwarth, U
    Stamm, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (2-3) : 161 - 177
  • [9] Jacoud J.L., 2000, DESPRIPTION QUALIFIC
  • [10] The maturing of nuclear fuel: Past to Accident Tolerant Fuel
    Karoutas, Zeses
    Brown, Jeffery
    Atwood, Andrew
    Hallstadius, Lars
    Lahoda, Edward
    Ray, Sumit
    Bradfute, Jeffrey
    [J]. PROGRESS IN NUCLEAR ENERGY, 2018, 102 : 68 - 78