Verification study of the FORE-2M nuclear/thermal-hydraulic analysis computer code
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Abstract The verification of the LMFBR core transient performance code, FORE-2M, was performed in two steps. Different components of the computation (individual models) were verified by comparing with analytical solutions and with results obtained from other conventionally accepted computer codes (e.g., TRUMP, LIFE, etc.). For verification of the integral computation method of the code, experimental data in TREAT, SEFOR and natural circulation experiments in EBR-II were compared with the code calculations. Good agreement was obtained for both of these steps. Confirmation of the code verification for undercooling transients is provided by comparisons with the recent FFTF natural circulation experiments.
[1] R. A. Markley,et al. Thermal analysis of liquid--metal fast breeder reactors , 1978 .
[2] R. A. Markley,et al. Natural convection analyses and verification for LMFBR cores , 1980 .
[3] R. A. Markley,et al. Review of pertinent thermal-hydraulic data for LMFBR core natural circulation analyses , 1980 .
[4] D D Freeman. SEFOR experimental results and applications to LMFBR's , 1973 .