Definition of the 6th Dynamic AER Benchmark - Main Steam Line Break in a NPP with VVER-440


Definition of the 6th Dynamic AER Benchmark - Main Steam Line Break in a NPP with VVER-440

Kliem, S.; Seidel, A.; Grundmann, U.

The 6th dynamic benchmark concerns a double ended break of one main steam line (asymmetric MSLB) in a VVER-440 plant. The core is at the end of its first cycle in full power conditions. The control rods of group K6 are at position 175 cm from bottom of the core. All other groups of control rods are out of the core. The initial state conditions of the core in the beginning of the transient are given. The isothermal re-criticality temperature of the core is defined to be 210°C. It should be achieved by tuning the worth of all control rods. Otherwise, own best estimate nuclear data are to be used. The main geometrical parameters of the plant and the characteristics of control and safety systems to be considered are given. Otherwise, own input data decks developed for a VVER-440 plant and for the applied codes can be used. The objective is to calculate the behaviour of the core during this re-criticality event using coupled codes, which combine a three-dimensional neutron kinetics code for the core with a thermohydraulics system code. This benchmark is a logical continuation of the work in the 5th dynamic benchmark. Additional new features include asymmetric operation of the feed water system, effects of coolant mixing in the reactor vessel, and the definition of a fixed isothermal re-criticality temperature for normalising the nuclear data.

  • Lecture (Conference)
    Tenth Symposium of AER on VVER Reactor Physics and Reactor Safety 2000, Moscow (Russia), 18.-22. September 2000, Proceedings pp. 749-762
  • Contribution to proceedings
    Tenth Symposium of AER on VVER Reactor Physics and Reactor Safety 2000, Moscow (Russia), 18.-22. September 2000, Proceedings pp. 749-762

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Publ.-Id: 3490