l Yield behavior of porous nuclear fuel (UO2)

被引:2
|
作者
Aravindan, S. [1 ,2 ]
Jalaldeen, S. [2 ]
Chellapandi, P. [2 ]
Swaminathan, N. [1 ]
机构
[1] Indian Inst Technol, Dept Mech Engn, Room 206, Madras 600036, Tamil Nadu, India
[2] Indira Gandhi Ctr Atom Res, Reactor Design Grp, Kalpakkam 603102, Tamil Nadu, India
关键词
Uranium dioxide; porous material; finite element method; yield surface; concrete damaged plasticity; FISSION-GAS RELEASE; PELLET-CLADDING INTERACTION; SINTERED URANIUM-DIOXIDE; PLASTIC-DAMAGE MODEL; ELASTIC PROPERTIES; ULTRASONIC VELOCITY; CONCRETE STRUCTURES; INTERNAL-PRESSURE; POPULATIONS; SIMULATION;
D O I
10.1080/15376494.2015.1059529
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Uranium dioxide (UO2) is one of the most common nuclear fuels. During burn-up, the fuel undergoes substantial microstructural changes including the formation of pressurized pores, thus becoming a porous material. These pores reduce the elastic modulus and alter the yield behavior of the material. In this work, a finite-element-based homogenization technique has been used to map the yield surface of UO2 with pressurized pores. Two scenarios are considered; in the first, the fuel matrix is a ductile material with a Von-mises type behavior, while in the second, the matrix is quasi brittle, which is simulated using the concrete damaged plasticity (CDP) model available in ABAQUS. For both of the scenarios, it is found that the yield strength decreases with an increase in porosity for a given internal pore pressure. For a given porosity, the yield surface shifts towards the negative hydrostatic axis in the Haigh-Westergard stress space with an increase in pore pressure. When the matrix is quasi brittle, the decrease in tensile hydrostatic strength is less than the increase in compressive hydrostatic strength, whereas in the case of a ductile matrix, the changes in the hydrostatic strengths are same. Furthermore, the shape of the yield surface changes from one deviatoric plane to another in both scenarios. Analytical equations, which are functions of pore pressure and porosity, are developed to describe the yield surface of porous UO2 while accounting for the changes in shape of the yield surface from one deviatoric plane to another. These yield functions can be used to predict the failure of porous UO2 fuel.
引用
收藏
页码:1149 / 1162
页数:14
相关论文
共 50 条
  • [41] Atomistic simulations of nuclear fuel UO2 with machine learning interatomic potentials
    Dubois, Eliott T.
    Tranchida, Julien
    Bouchet, Johann
    Maillet, Jean-Bernard
    PHYSICAL REVIEW MATERIALS, 2024, 8 (02):
  • [42] THE EFFECT OF PH ON THE CORROSION OF NUCLEAR-FUEL (UO2) IN OXYGENATED SOLUTIONS
    SUNDER, S
    SHOESMITH, DW
    LEMIRE, RJ
    BAILEY, MG
    WALLACE, GJ
    CORROSION SCIENCE, 1991, 32 (04) : 373 - 386
  • [43] Upscaled elasticity modulus for nuclear fuel pellet (UO2) with porosity effects
    Centeno-Perez, J.
    Aguilar-Madera, C. G.
    Espinosa-Paredes, G.
    Herrera-Hernandez, E. C.
    Perez-Valseca, A. D.
    JOURNAL OF NUCLEAR MATERIALS, 2022, 568
  • [44] Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel
    Tonks, Michael R.
    Simon, Pierre-Clement A.
    Hirschhorn, Jacob
    JOURNAL OF NUCLEAR MATERIALS, 2021, 543
  • [45] Effects of α and γ radiolysis of water on alteration of the spent UO2 nuclear fuel matrix
    Jégou, C
    Broudic, V
    Poulesquen, A
    Bart, JM
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXVII, 2004, 807 : 391 - 396
  • [46] NUCLEAR MICROPROBE STUDY OF THE LEACHING BEHAVIOR OF SINTERED UO2 IN GROUNDWATER
    TROCELLIER, P
    GALLIEN, JP
    CACHOIR, C
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 1995, 104 (1-4): : 547 - 551
  • [47] Preparation, characterisation and dissolution of a CeO2 analogue for UO2 nuclear fuel
    Stennett, Martin C.
    Corkhill, Claire L.
    Marshall, Luke A.
    Hyatt, Neil C.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 432 (1-3) : 182 - 188
  • [48] MECHANISMS OF LEACHING AND DISSOLUTION OF UO2 FUEL
    JOHNSON, LH
    SHOESMITH, DW
    LUNANSKY, GE
    BAILEY, MG
    TREMAINE, PR
    NUCLEAR TECHNOLOGY, 1982, 56 (02) : 238 - 253
  • [49] ENGINEERING FOR FISSION GAS IN UO2 FUEL
    LEWIS, WB
    NUCLEAR APPLICATIONS, 1966, 2 (02): : 171 - &
  • [50] TEMPERATURE DISTRIBUTION IN UO2 FUEL ELEMENTS
    ROBERTSON, JAL
    ROSS, AM
    NOTLEY, MJF
    MACEWAN, JR
    JOURNAL OF NUCLEAR MATERIALS, 1962, 7 (03) : 225 - 262