2HSU Y Y, WANGZY, UNALC, et al. Scal- ing modeling for small break LOCA test facilities [J]. Nuclear Engineering and Design, 1990, 122 (1-3): 175-194.
3KOCAMUSTAFAOGULLARI G, ISHII M. Scaling criteria for two-phase flow natural and forced convection loop and their application to conceptual 2 X 4 simulation loop design, NUREG/CR-3420, ANL83-61 [R].America: Argonne National Laboratory, 1983.
5NAHAVANDI A N, CASTELLNAN F S, MO- RADKHANIAN E N. Scaling laws for modeling nuclear reactor systems[J]. Nuclear Science and Engineering, 1979, 72(1): 75-83.
6ZUBER N, WILSON G E, ISHII M, et al. An integrated structure and scaling methodology for severe accident technical issue resolution: Devel- opment of methodology[J]. Nuclear Engineering and Design, 1998, 186(1): 1-21.
7Jr REYES J N, HOCHREITER L. Scaling anal ysis for the OSU AP600 facility(APEX)[J].Nu clear Engineering and Design, 1998, 186(1): 53-109.
8KOCAMUSTAFAOGULLARI G, ISHII M. Scaling of two-phase flow transients using re- duced pressure system and stimulantfluid[J]. Nuclear Engineering and Design, 1987, 104(2) : 121-132.
9PARK H S, CHOI K Y, CHO S. Major findings from LBLOCA reflood tests using the ATLAS facility[J]. Nuclear 2010, 240(12): 3 920 Engineering and Design, 3 929.
10ISHII M, REVANKAR S T, LEONARDI T, et al. The threeqevel scaling approach with applica- tion to the Purdue University Multi Dimensional Integral Test Assembly (PUMA)[J].uclear Engineering and Design, 1998, 186(1-2): 177-211.
