Fission products at the fuel-cladding interface of PWR fuel rods: morphological and chemical study

被引:0
|
作者
Schneider, C. [1 ,2 ]
Fayette, L. [1 ]
Zacharie-Aubrun, I. [1 ]
Blay, T. [1 ]
Onofri-Marroncle, C. [1 ]
Sabathier, C. [1 ]
Drouan, D. [1 ]
Sercombe, J. [1 ]
Favergeon, J. [3 ]
Chevalier, S. [4 ]
机构
[1] CEA, DES, IRESNE, DEC, F-13108 St Paul Les Durance, France
[2] Paul Scherrer Inst, Lab Nucl Mat, Forsch Str 111, CH-5232 Villigen, Switzerland
[3] Univ Technol Compiegne, Alliance Sorbonne Univ, Ctr Rech Royallieu, Lab Roberval, CS 60319, F-60203 Compiegne, France
[4] Univ Bourgogne Franche Comte, CNRS, UMR 6303, ICB, 9 Ave Savary, F-21078 Dijon, France
关键词
Spent fuel; Fission products; Fuel-cladding interface; Zirconia; Zirconium oxide; FIB-SEM tomography; STEM-EDS chemical analysis; RU-RH-PD; MO-RU; IMAGE; PARTICLES; CORROSION; PLATFORM; STATE; UO2;
D O I
10.1016/j.jnucmat.2023.154600
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
During irradiation in light water reactors, numerous fission products are produced by the fission reactions. At the periphery of the fuel, these elements implant by recoil in the cladding inner oxide layer (zirconia) located at the fuel-cladding interface. In the present study, two irradiated UO2 fuel rods with different burnups (37.3 and 61.4 GWd/tU) have been analyzed. The coupling of FIB-SEM tomography and S/TEM-EDS chemical analyses allowed 3D analysis of the distribution, sizes, shape and chemical composition of the bubbles and precipitates of fission products in zirconia. The fission product structure, observed in the two samples was quite similar. A complex morphology of the fission product agglomerates have been highlighted. They are organized in three parts: the bubble (Xe), the deposit (Cs, I) and the metallic precipitates (Mo, Tc, Ru, Rh, Pd, Sn). Tellurium is partly found with the deposit, but also with the metallic precipitates. Different kind of bubbles have been observed, classified by size, potentially linked to different steps of growth. In particular, Xe form bubbles arranged in three pop-ulations: sub and/or nanobubbles within the grains and along the grain boundaries (< 1 nm), larger bubbles (a few nanometers to a few tens of nanometers) anchored to the metallic precipitates, and finally, much larger bubbles (several tens to several hundreds of nanometers), which are part of more complex systems, and are also stuck to metallic precipitates.
引用
收藏
页数:17
相关论文
共 50 条
  • [41] CFD study on mechanisms of fission gas burst release from defective fuel rods of a typical PWR
    Dong, Bing
    Li, Chenyue
    Li, Leihao
    Yin, Junlian
    Wang, Dezhong
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 140
  • [42] FUEL-CLADDING GAP-CONDUCTANCE MODEL FOR LMFBR FUEL-ELEMENTS
    CHOW, LSH
    BILLONE, MC
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 170 - 171
  • [43] FUEL-CLADDING CHEMICAL INTERACTION IN URANIUM-PLUTONIUM OXIDE FAST-REACTOR FUEL-PINS
    FEE, DC
    JOHNSON, CE
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1981, 96 (1-2) : 80 - 104
  • [44] FUEL-CLADDING CHEMICAL INTERACTIONS IN LOW-DENSITY (U,PU)O2 FUEL PINS
    COX, CM
    OLSEN, AR
    FITTS, RB
    LONG, EL
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 173 - &
  • [45] Fuel-Cladding Interaction Between U-Pu-Zr Fuel and Fe
    Aitkaliyeva, Assel
    Madden, James W.
    Miller, Brandon D.
    Papesch, Cynthia A.
    Cole, James I.
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS E-MATERIALS FOR ENERGY SYSTEMS, 2015, 2 (04): : 220 - 228
  • [46] SELECTION OF FUEL-CLADDING MATERIALS FOR NUCLEAR SUPERHEAT REACTORS
    SPALARIS, CN
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1965, 8 (01): : 121 - &
  • [47] IMPLICATIONS OF ADVANCED FUEL-CLADDING CONCEPTS ON GCFR DESIGN
    FAZZOLARE, RA
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 521 - 522
  • [48] ROLE OF CESIUM IODIDE ON DEVELOPMENT OF FUEL-CLADDING REACTIONS
    AUBERT, M
    CALAIS, D
    LEBEUZE, R
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1976, 60 (03) : 279 - 290
  • [49] FUEL-CLADDING MECHANICAL INTERACTION IN FAST BREEDER FUEL-PINS - OBSERVATIONS AND ANALYSIS
    DIENST, W
    GUERIN, Y
    GATESOUPE, JP
    MULLERLYDA, I
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1980, 91 (01) : 73 - 84
  • [50] THE RADIAL-DISTRIBUTION OF FISSION GASES AND OTHER FISSION-PRODUCTS IN IRRADIATED PWR FUEL
    MANZEL, R
    SONTHEIMER, F
    WURTZ, R
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1984, 126 (02) : 132 - 143