YANG Yun, ZHAO Lei, HU Wenjun, CHAI Xiang, CHENG Xu. CFD Analysis on Flow Blockage Accident of Single Subassembly for Sodium Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2019, 53(12): 2398-2404. DOI: 10.7538/yzk.2018.youxian.0891
Citation: YANG Yun, ZHAO Lei, HU Wenjun, CHAI Xiang, CHENG Xu. CFD Analysis on Flow Blockage Accident of Single Subassembly for Sodium Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2019, 53(12): 2398-2404. DOI: 10.7538/yzk.2018.youxian.0891

CFD Analysis on Flow Blockage Accident of Single Subassembly for Sodium Cooled Fast Reactor

More Information
  • Sodium cooled fast reactors mostly use metal wires to space the fuel assembly, and slender and narrow flow channels are easy to accumulate corrosive sediments, which tends to cause the local sodium boiling and heat transfer deterioration of cladding. In this paper, single subassembly blockage accidents were numerically simulated by the commercial computation fluid dynamics (CFD) software STAR-CCM+, temperature of cladding inner face and coolant axial velocity distribution around blockage were analyzed and compared with the result in no-blockage case. The calculation results show that the harm of solid media blockage is more serious than that of porous media. The local highest point of cladding peak temperature is always located at the centric position of the blockage in the solid media blockage accidents. But in the porous media blockage accidents, the cladding peak temperature is found in the downstream of blockage and tends to move further downstream with the increase of blockage area. The blockage porosity is seen to exhibit significant influence on the maximum cladding temperature difference in the downstream of blockage. Further, the maximum cladding temperature difference is smaller if the porosity is larger.
  • [1]
    ICHIMIYA M. The status of generation Ⅳ sodium-cooled fast reactor technology development and its future project[J]. Energy Procedia, 2011, 7(2): 79-87.
    [2]
    徐銤,杨红义. 钠冷快堆及其安全特性[J]. 物理,2016,45(9):561-568.XU Mi, YANG Hongyi. Safety properties of sodium cooled fast reactors[J]. Physics, 2016, 45(9): 561-568(in Chinese).
    [3]
    徐銤. 中国实验快堆的安全特性[J]. 核科学与工程,2011,31(2):116-126.XU Mi. Safety properties of China Experimental Fast Reactor[J]. Chinese Journal of Nuclear Science and Engineering, 2011, 31(2): 116-126(in Chinese).
    [4]
    RAJ M N, VELUSAMY K, MAITY R K. Thermal hydraulic investigations on porous blockage in a prototype sodium cooled fast reactor fuel pin bundle[J]. Nuclear Engineering and Design, 2016, 303: 88-108.
    [5]
    GNADT P A, CARBAJO J J, DEARING J F, et al. Sodium boiling experiments in the THORS facility[J]. Nuclear Engineering and Design, 1984, 82(2): 241-280.
    [6]
    FONTANA M H, MACPHERSON R E, GNADT P A, et al. Temperature distribution in the duct wall and at the exit of a 19-rod simulated LMFBR fuel assembly (FFM Bundle 2A)[J]. Nuclear Science and Engineering, 1974, 24(2): 176-200.
    [7]
    OLIVE J, JOLAS P. Internal blockage in a fissile super-phenix type subassembly: The scarlet experiments and their interpretation by the Cafca-NA3 code[J]. Nuclear Energy, 1990, 29(4): 287-293.
    [8]
    RASU N G, VELUSAMY K, SUNDARARAJAN T, et al. Thermal hydraulic effect of porous blockage in fuel subassembly of sodium cooled fast reactor[J]. Annals of Nuclear Energy, 2014, 70(3): 64-81.
    [9]
    ERGUN S. Fluid flow through packed columns[J]. Chemical Engineering Progress, 1952, 48(2): 89-94.
    [10]
    MENTER F R. Two-equation eddy-viscosity turbulence models for engineering applications[J]. AIAA Journal, 1994, 32(8): 1598-1605.
    [11]
    CHANG W P, JIN Y, CHOI C W, et al. MATRA-LMR-FB assessment with THORS bundle 2B experiments[J]. Nuclear Engineering and Design, 2015, 282: 15-27.

Catalog

    Article views (539) PDF downloads (1202) Cited by()

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return