KORSAR/GP and SOCRAT/V1 codes’ validation for the loss of cooling at spent fuel pool conditions

2021/02/09 by M.M. Bedretdinov, M. M. Bedretdinov, О. Е. Степанов +4 · 1 citation
Engineering · #Nuclear Engineering Thermal-Hydraulics #Nuclear reactor physics and engineering #Nuclear and radioactivity studies

paper · doi:10.1016/j.nucengdes.2021.111089

Citations

• Experimental investigation of the thermal hydraulics of a spent fuel pool under loss of active heat removal conditions

Cited by

• Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions