|
[1]
|
Olander, D.R. (1976) Fundamental Aspects of Nuclear Reactor Fuel Elements. Technical Information Center-Energy Re-search and Development Administration, University of California, Berkeley. [Google Scholar] [CrossRef]
|
|
[2]
|
Losonen, P. (2000) On the Behavior of Intragranular Fission Gas in UO2 Fuel. Journal of Nuclear Materials, 280, 56-72. [Google Scholar] [CrossRef]
|
|
[3]
|
Booth, A.H. (1957) A Method of Calculating Fission Gas Diffusion from UO2 Fuel and Its Application to the X-2-f Loop Test. Rap-port Atomic Energy of Canada Limited CRDC-712.
|
|
[4]
|
Speight, M.V. (1969) A Calculation on the Migration of Fis-sion Gas in Material Exhibiting Precipitation and Re-Solution of Gas Atoms under Irradiation. Nuclear Science and En-gineering, 37, 180-185. [Google Scholar] [CrossRef]
|
|
[5]
|
Forsberg, K. and Massih, A.R. (1985) Diffusion Theory of Fission Gas Migration in Irradiated Nuclear Fuel UO2. Journal of Nuclear Materials, 135, 140-148. [Google Scholar] [CrossRef]
|
|
[6]
|
Pastore, G., Luzzi, L., Di Marcello, V. and Van Uffelen, P. (2013) Physics-Based Modelling of Fission Gas Swelling and Release in UO2 Applied to Integral Fuel Rod Analysis. Nuclear Engineering and Design, 256, 75-86. [Google Scholar] [CrossRef]
|
|
[7]
|
崔羿, 丁淑蓉, 赵云妹, 等. 考虑晶界扩散和晶界联合的UO2燃料裂变气体模型[J]. 核动力工程, 2012(S2): 9-12+42.
|
|
[8]
|
Geelhood, K.J., Luscher, W.G., Beyer, C.E., et al. (2015) FRAPCON-4.0: A Computer Code for the Calculation of Steady-State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. Pacific Northwest National Laboratory, United States.
|
|
[9]
|
Hales, J.D., Williamson, R.L., Novascone, S.R., et al. (2016) BISON Theory Manual, the Equations Behind Nuclear Fuel Analysis. Idaho National Laboratory, United States. [Google Scholar] [CrossRef]
|
|
[10]
|
Rashid, Y., Dunham, R. and Montgomery, R. (2004) Fuel Analysis and Licensing Code: FALCON MOD01: Volume 1: Theoretical and Numerical Bases. EPRI, Palo Alto.
|
|
[11]
|
Turnbull, J.A. (1974) The Effect of Grain Size on the Swelling and Gas Release Properties of UO2 During Irradiation. Journal of Nuclear Materials, 50, 62-68. [Google Scholar] [CrossRef]
|
|
[12]
|
Hermansson, P. and Massih, A.R. (2002) An Effective Meth-od for Calculation of Diffusive Flow in Spherical Grain. Journal of Nuclear Materials, 304, 204-211. [Google Scholar] [CrossRef]
|
|
[13]
|
Dowling, D.M., White, R.J. and Tucker, M.O. (1982) The Effect of Irradiation-Induced Re-Solution on Fission Gas Release. Journal of Nuclear Material, 110, 37-46. [Google Scholar] [CrossRef]
|