Aqueous leaching of Cr2O3-doped UO2 spent nuclear fuel under oxidizing conditions

被引:4
|
作者
Barreiro-Fidalgo, Alexandre [1 ]
Roth, Olivia [1 ]
Evins, Lena Zetterstrom [2 ]
Spahiu, Kastriot [2 ]
机构
[1] Studsvik Nucl AB, S-61182 Nykoping, Sweden
[2] Swedish Nucl Fuel & Waste Management Co SKB, S-16903 Solna, Sweden
关键词
The Swedish nuclear Fuel and Waste Management Company (SKB) is greatly acknowledged for financial support. The authors would like to thank Framatome for their contribution in this project. Special thanks to everyone involved in this project at Studsvik for their excellent work;
D O I
10.1557/s43580-021-00043-y
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Understanding the leaching behavior of spent nuclear fuel is crucial for the safety assessment of deep geological repositories to dispose spent nuclear fuel. During the last decades, new types of nuclear fuel are being introduced in commercial reactors. These new fuels with additives such as chromium oxide (Cr2O3) have an impact on the UO2 microstructure and therefore might affect properties relevant to the safety assessment. The main goal of this investigation is to understand the effects of Cr-doping on the instant release fraction of fission products. A sample consisting of fuel fragments and separated cladding was leached in simplified groundwater under aerated conditions at Studsvik's Hot Cell Laboratory. Data from leaching experiments performed on Cr-doped fuel manufactured by Framatome are presented and compared to other commercial Cr-doped fuel manufactured by Westinghouse (Advanced DOped Pellet Technology, ADOPT) and standard UO2 fuel.
引用
收藏
页码:103 / 106
页数:4
相关论文
共 50 条
  • [21] Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions
    dePablo, J
    Casas, I
    Gimenez, J
    Marti, V
    Torrero, ME
    JOURNAL OF NUCLEAR MATERIALS, 1996, 232 (2-3) : 138 - 145
  • [22] ALTERATION OF NATURAL UO2 UNDER OXIDIZING CONDITIONS FROM SHINKOLOBWE, KATANGA, ZAIRE - A NATURAL ANALOG FOR THE CORROSION OF SPENT FUEL
    FINCH, RJ
    EWING, RC
    RADIOCHIMICA ACTA, 1991, 52-3 : 395 - 401
  • [23] Fission product speciation across a UO2 spent nuclear fuel
    Klosek, V.
    Hunault, M. O. J. Y.
    Schlutig, S.
    Tomczak, W.
    Rochedy, M.
    Solari, P. L.
    Noirot, J.
    JOURNAL OF NUCLEAR MATERIALS, 2023, 586
  • [24] OXIDATION BEHAVIOR OF SPENT UO2 FUEL
    CAMPBELL, TK
    GILBERT, ER
    THORNHILL, CK
    WRONA, BJ
    NUCLEAR TECHNOLOGY, 1989, 84 (02) : 182 - 195
  • [25] 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
  • [26] α-radiolysis and α-radiation damage effects on UO2 dissolution under spent fuel storage conditions
    Rondinella, VV
    Matzke, H
    Cobos, J
    Wiss, T
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXII, 1999, 556 : 447 - 454
  • [27] Modeling spent nuclear UO2-fuel dissolution under repository conditions
    De Pablo, J
    Casas, I
    Rovira, M
    ENVIRONMENTAL CHALLENGES OF NUCLEAR DISARMAMENT, 2000, 29 : 93 - 102
  • [28] Why do UO2 secondary phases and spent nuclear fuel float?
    McNamara, BK
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 2003, 225 : U646 - U647
  • [29] 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
  • [30] SIMFUEL and UO2 solubility and leaching behaviour under anoxic conditions
    Quinones, J
    Garcia-Serrano, J
    Serrano, JA
    Diaz-Arocas, P
    Almazan, JLR
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXI, 1998, 506 : 247 - 252