1. Thurgood, M.J. et al. 1983. COBRA/TRAC: A thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems, 365 Tech. Rep. NUREG/CR-3046, PNL-4385, US Nuclear Regulatory Commission.
2. Avramova, M.N., Salko, R.K. et al. 2017. CTF theory manual, Tech. Rep. CASL-U-2017-1263-000, CASL/NCSU (January 2017).
3. COBRA-IE: A new sub-channel analysis code;Aumiller,2015
4. Burns, C.J., Aumiller, D.L., 2007. COBRA-IE evaluation by simulation of the NUPEC BWR full-size fine-mesh bundle test BFBT, Tech. Rep. B-T-3653, Bechtel Bettis, Inc.
5. Development of Spatially-selective, Nonlinear Refinement Algorithm for Thermal-Hydraulic Safety Analysis;Lloyd,2014