共 7 条
[1]
Chauliac C., Aragones J.M., Bestion D., Et al., NURESIM: A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis, Nuclear Engineering and Design, 241, 9, pp. 3416-3426, (2011)
[2]
Studer E., Beccantini A., Gounanda S., Et al., CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal-hydraulic analyzes of gas cooled reactors, Nuclear Engineering and Design, 237, 15, pp. 1814-1828, (2007)
[3]
Liu Y., Zhang H., Jia B., Research on coupling of COBRA-IV and CFX, Nuclear Power Engineering, 31, 2, pp. 43-46, (2010)
[4]
Anderson N., Hassan Y., Schultz R., Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code, Nuclear Engineering and Design, 238, 1, pp. 274-279, (2008)
[5]
(2008)
[6]
(2007)
[7]
Xia B., Yang P., Wang L., Et al., Core preliminary conceptual design of supercritical water-cooled CSR1000, Nuclear Power Engineering, 34, 1, pp. 9-14, (2013)