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APPLICATION OF THE KORSAR AND RELAP CODES FOR NUMERICAL ANALYSIS OF REACTOR EXPERIMENTS "PETTY LEAKAGE"

V. M. Makhin, I. I. Semidotskyi
VANT. Ser.: Mat. Mod. Fiz. Proc 2004. Вып.4. С. 88-93.

The results of numerical research of modes of testing the seven- and nineteen-element fuel element MIR reactor on the loop facility PVP-2 by using the KORSAR/V1.008.000 and RELAP 5/MOD3.2 codes. Fuel elements were tested in the mode, simulating final stages of accidents on WWER with loss of heat carriers and fuel element upper part dehydration (petty leakage). The code conservatism for numerical analysis of examined modes was estimated.









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