Volume 35 Issue 11
Oct.  2023
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Wang Huacai, Cheng Huanlin, Song Wulin, et al. Raman characteristic analysis of oxidation of fuel pellets for intact and leaked pressurized water reactors fuel rods with different burnup[J]. High Power Laser and Particle Beams, 2023, 35: 116003. doi: 10.11884/HPLPB202335.230047
Citation: Wang Huacai, Cheng Huanlin, Song Wulin, et al. Raman characteristic analysis of oxidation of fuel pellets for intact and leaked pressurized water reactors fuel rods with different burnup[J]. High Power Laser and Particle Beams, 2023, 35: 116003. doi: 10.11884/HPLPB202335.230047

Raman characteristic analysis of oxidation of fuel pellets for intact and leaked pressurized water reactors fuel rods with different burnup

doi: 10.11884/HPLPB202335.230047
  • Received Date: 2023-03-08
  • Accepted Date: 2023-09-19
  • Rev Recd Date: 2023-09-19
  • Available Online: 2023-11-05
  • Publish Date: 2023-11-11
  • To study the oxidation and phase structure of fuel pellets for both intact and leak pressurized water reactors fuel rods with different burnup, Raman spectroscopy was used to analyze the intact fuel rods with 14 GW·d·t−1 and 41 GW·d·t−1 burnup as well as the leak fuel rods with 14 GW·d·t−1 and 41 GW·d·t−1 burnup. Evaluation of the reactivity and structural changes of the fuels based on different laser powers are provided locally. The results show that the increase in laser power would not cause oxidation of UO2. The intact fuel rod UO2 pellets with 14 GW·d·t−1 and 45 GW·d·t−1 burnup consist of UO2, U4O9 and U3O8, and the oxidation of fuel pellet in peripheral zone is higher than that of the internal area. The leak fuel rod UO2 pellets with 14 GW·d·t−1 and 41 GW·d·t−1 burnup have undergone restructuring and formed columnar grains, which consist of UO2 and U3O8. The increase of burnup and leakage of fuel rods can promote the oxidation of UO2 pellets, but the main phase structure of the fuel pellets will not change.
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  • [1]
    唐纳德·奥兰德. 核反应堆燃料元件基本问题[M]. 李恒德, 潘金生, 柳百新, 等, 译. 北京: 原子能出版社, 1983: 242-243

    Olander D R. Fundamental aspects of nuclear reactor fuel elements[M]. Li Hengde, Pan Jinsheng, Liu Baixin, et al, trans. Beijing: Atomic Energy Press, 1983: 242-243
    [2]
    Skomurski F N, Wang J W, Ewing R C, et al. Charge distribution and oxygen diffusion in hyperstoichiometric uranium dioxide UO2+ x ( x ≤ 0.25)[J]. Journal of Nuclear Materials, 2013, 434(1/3): 422-433.
    [3]
    周邦新. 核反应堆材料(上册)[M]. 上海: 上海交通大学出版社, 2021: 55

    Zhou Bangxin. Nuclear reactor materials (Book 1)[M]. Shanghai Jiao Tong University Press, 2021: 55
    [4]
    Jegou C, Gennisson M, Peuget S, et al. Raman micro-spectroscopy of UOX and MOX spent nuclear fuel characterization and oxidation resistance of the high burn-up structure[J]. Journal of Nuclear Materials, 2015, 458: 343-349. doi: 10.1016/j.jnucmat.2014.12.072
    [5]
    Elorrieta J M, Bonales L J, Naji M, et al. Laser-induced oxidation of UO2: a Raman study[J]. Journal of Raman Spectroscopy, 2018, 49(5): 878-884. doi: 10.1002/jrs.5347
    [6]
    Mohun R, Desgranges L, Jégou C, et al. Quantification of irradiation-induced defects in UO2 using Raman and positron annihilation spectroscopies[J]. Acta Materialia, 2019, 164: 512-519. doi: 10.1016/j.actamat.2018.10.044
    [7]
    Desgranges L, Guimbretière G, Simon P, et al. Annealing of the defects observed by Raman spectroscopy in UO2 irradiated by 25 MeV He2+ ions[J]. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2014, 327: 74-77.
    [8]
    Desgranges L, Canizares A, Simon P. Annealing of the Raman defect peaks in He-implanted UO2[J]. Journal of Nuclear Materials, 2022, 559: 153405. doi: 10.1016/j.jnucmat.2021.153405
    [9]
    王华才, 程焕林, 宋武林, 等. 压水堆完整和破损燃料棒燃料包壳化学相互作用层拉曼特征分析[J]. 原子能科学技术, 2023, 57(3):619-629

    Wang Huacai, Cheng Huanlin, Song Wulin, et al. Raman characteristics analysis of fuel-cladding chemical interaction layer for intact and leak PWR fuel rods[J]. Atomic Energy Science and Technology, 2023, 57(3): 619-629
    [10]
    Ciszak C, Mermoux M, Miro S, et al. Micro-Raman analysis of the fuel-cladding interface in a high burnup PWR fuel rod[J]. Journal of Nuclear Materials, 2017, 495: 392-404. doi: 10.1016/j.jnucmat.2017.08.038
    [11]
    Jégou C, Caraballo R, De Bonfils J, et al. Oxidizing dissolution of spent MOX47 fuel subjected to water radiolysis: solution chemistry and surface characterization by Raman spectroscopy[J]. Journal of Nuclear Materials, 2010, 399(1): 68-80. doi: 10.1016/j.jnucmat.2010.01.004
    [12]
    Jégou C, Caraballo R, Peuget S, et al. Raman spectroscopy characterization of actinide oxides (U1− y Pu y )O2: resistance to oxidation by the laser beam and examination of defects[J]. Journal of Nuclear Materials, 2010, 405(3): 235-243. doi: 10.1016/j.jnucmat.2010.08.005
    [13]
    Manara D, Renker B. Raman spectra of stoichiometric and hyperstoichiometric uranium dioxide[J]. Journal of Nuclear Materials, 2003, 321(2/3): 233-237.
    [14]
    唐纳德·奥兰德. 核反应堆燃料元件基本问题[M]. 李恒德, 潘金生, 柳百新, 等, 译. 北京: 原子能出版社, 1983: 245

    Olander D R. Fundamental aspects of nuclear reactor fuel elements[M]. Li Hengde, Pan Jinsheng, Liu Baixin, et al, trans. Beijing: Atomic Energy Press, 1983: 245
    [15]
    Palacios M L, Taylor S H. Characterization of uranium oxides using in situ micro-Raman spectroscopy[J]. Applied Spectroscopy, 2000, 54(9): 1372-1378. doi: 10.1366/0003702001951057
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