engleski

Contribution of FER to the WP4: summary report for the first year, TA2/SARNET ASCOM Technical report

The ASTEC V2.1 computer code, IRSN all rights reserved, was used to simulate a severe accident sequence in the Krško NPP, a two-loop PWR type nuclear power plant. The analysis was conducted in two steps. First, the steady state calculation was performed in order to confirm the applicability of the plant model and to obtain correct initial conditions for the accident analysis. In order to achieve that, the operation of regulation systems was modelled. Parameters which were subjected to regulation were the pressurizer pressure, the pressurizer narrow range level and steam mass flow rates in the steam lines. The second step was the calculation of the station blackout (SBO) accident with the leakage of the primary coolant through degraded reactor coolant pump seals, which was a small break LOCA without makeup capability. The analyzed SBO scenario included the loss of both off-site and on-site AC power. The only components available were the passive accumulators.

ASTEC ; PWR ; SBO ; severe accident

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