TY - JOUR
T1 - Numerical investigations on the melting process of the nuclear fuel rod in RIAs and LOCAs
AU - Tang, Jiannan
AU - Huang, Mei
AU - Zhao, Yuanyuan
AU - Maqsood, Saad
AU - Ouyang, Xiaoping
N1 - Publisher Copyright:
© 2018 Elsevier Ltd
PY - 2018/9
Y1 - 2018/9
N2 - In light water reactor, melting of nuclear fuel rod (NFR) is critical. Therefore, this issue needs to be simulated and analyzed with different accidental conditions. In this paper, one-dimensional model is build and used to simulate the melting process of NFR in nuclear core. The numerical model includes three regions; these are Uranium dioxide fuel pellet, Helium layer and Zirconium alloy cladding. Due to huge temperature gradient in radial direction of NFR, material properties which include specific heat, thermal conductivity and density are non-linear and depends on temperature. In addition to this the convection and radiation heat transfer are also considered in the Helium layer region. To solve the enthalpy formulation of melting process, the Half Boundary Method (HBM) is used in this paper. The HBM is accurate, efficient and save calculational memory. The melting process of fuel rod is simulated during Reactivity-Initiated Accidents (RIAs) and Loss-Of-Coolant Accidents (LOCAs). The results showed us that if RIA happens melting will first take place at the center of pellet and in case of LOCA, melting will begin inside cladding.
AB - In light water reactor, melting of nuclear fuel rod (NFR) is critical. Therefore, this issue needs to be simulated and analyzed with different accidental conditions. In this paper, one-dimensional model is build and used to simulate the melting process of NFR in nuclear core. The numerical model includes three regions; these are Uranium dioxide fuel pellet, Helium layer and Zirconium alloy cladding. Due to huge temperature gradient in radial direction of NFR, material properties which include specific heat, thermal conductivity and density are non-linear and depends on temperature. In addition to this the convection and radiation heat transfer are also considered in the Helium layer region. To solve the enthalpy formulation of melting process, the Half Boundary Method (HBM) is used in this paper. The HBM is accurate, efficient and save calculational memory. The melting process of fuel rod is simulated during Reactivity-Initiated Accidents (RIAs) and Loss-Of-Coolant Accidents (LOCAs). The results showed us that if RIA happens melting will first take place at the center of pellet and in case of LOCA, melting will begin inside cladding.
KW - Half-boundary method
KW - LOCA
KW - Melting process
KW - Nuclear fuel rod
KW - RIA
UR - https://www.scopus.com/pages/publications/85045207833
U2 - 10.1016/j.ijheatmasstransfer.2018.04.001
DO - 10.1016/j.ijheatmasstransfer.2018.04.001
M3 - 文章
AN - SCOPUS:85045207833
SN - 0017-9310
VL - 124
SP - 990
EP - 1002
JO - International Journal of Heat and Mass Transfer
JF - International Journal of Heat and Mass Transfer
ER -