Micromechanical properties of TRISO coatings by in-situ high temperature nanoindentation and microcantilever fracture

被引:2
作者
Leide, Alex [1 ,2 ]
Hintsala, Eric [3 ]
Davies, Mark [4 ]
Goddard, David T. [5 ]
Liu, Dong [2 ]
机构
[1] UK Atom Energy Author, Culham Sci Ctr, Abingdon OX14 3DB, England
[2] Univ Bristol, Sch Phys, Tyndall Ave, Bristol BS8 1TL, England
[3] Bruker Nano Surfaces & Metrol, 9625 West 76th St, Eden Prairie, MN USA
[4] Ultra Safe Nucl Corp, St Helens, England
[5] Natl Nucl Lab, Preston Lab, Preston PR4 0XJ, England
关键词
TRISO; Nanoindentation; Micromechanics; Fracture; SiC; COATED FUEL-PARTICLES; SILICON-CARBIDE; MECHANICAL-PROPERTIES; SPHERICAL-PARTICLES; SIC COATINGS; LAYER; PERFORMANCE; PARAMETERS; STRENGTH; BEHAVIOR;
D O I
10.1016/j.jeurceramsoc.2023.12.056
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Coated nuclear fuel particles, most commonly tri-structural isotropic (TRISO), are intended for use in advanced high temperature reactors. It is vital to understand the mechanical properties of each coating layer to accurately predict the performance of these fuel particles and how these might change at each stage of their lifecycle. This paper reports results of in-situ nanoindentation, with an emphasis on the structural SiC layer, along with microcantilever testing of the critical SiC-IPyC interface. At 1000 C-degrees the hardness of the SiC layer is similar to 75% lower than at room temperature implying significantly more plasticity at the reactor operating temperature. The elastic modulus was slightly lower at 1000 C-degrees than at room temperature. Microcantilever fracture at the SiC-IPyC interface shows that failure occurs within the pyrolytic carbon layer rather than an interfacial "debonding" with a strength similar to that of bulk pyrolytic carbon.
引用
收藏
页码:3112 / 3120
页数:9
相关论文
共 40 条
  • [1] A logical approach for zero-rupture Fully Ceramic Microencapsulated (FCM) fuels via pressure-assisted sintering route
    Ang, Caen
    Snead, Lance
    Kato, Yutai
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2020, 531
  • [2] Residual stresses in as-manufactured TRISO Coated Particle Fuel (CPF)
    Battistini, Angelo
    Haynes, Thomas A.
    Shepherd, Daniel
    Wenman, Mark R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2023, 586
  • [3] BOKROS JC, 1977, CARBON, V15, P355, DOI 10.1016/0008-6223(77)90324-4
  • [4] CRUSHING BEHAVIOR OF HIGH-TEMPERATURE REACTOR COATED FUEL PARTICLES
    BRIGGS, A
    DAVIDGE, RW
    PADGETT, C
    QUICKENDEN, S
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1976, 61 (03) : 233 - 242
  • [5] Evaluation of Fracture Stress for the SiC Layer of TRISO-Coated Fuel Particles Using a Modified Crush Test Method
    Byun, Thak Sang
    Hunn, John D.
    Miller, James H.
    Snead, Lance L.
    Kim, Jin Weon
    [J]. INTERNATIONAL JOURNAL OF APPLIED CERAMIC TECHNOLOGY, 2010, 7 (03) : 327 - 337
  • [6] Multimillion-atom nanoindentation simulation of crystalline silicon carbide: Orientation dependence and anisotropic pileup
    Chen, Hsiu-Pin
    Kalia, Rajiv K.
    Nakano, Aiichiro
    Vashishta, Priya
    Szlufarska, Izabela
    [J]. JOURNAL OF APPLIED PHYSICS, 2007, 102 (06)
  • [7] Crush strength of silicon carbide coated TRISO particles: Influence of test method and process variables
    Cromarty, R. D.
    van Rooyen, G. T.
    de Villiers, J. P. R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 445 (1-3) : 30 - 36
  • [8] Coated particle fuel: Historical perspectives and current progress
    Demkowicz, Paul A.
    Liu, Bing
    Hunn, John D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 515 : 434 - 450
  • [9] Measuring fracture toughness of coatings using focused-ion-beam-machined microbeams
    Di Maio, D
    Roberts, SG
    [J]. JOURNAL OF MATERIALS RESEARCH, 2005, 20 (02) : 299 - 302
  • [10] High-Temperature Nanoindentation of SiC/SiC Composites
    Frazer, D.
    Deck, C. P.
    Hosemann, P.
    [J]. JOM, 2020, 72 (01) : 139 - 144