Experiments on main steam line break in the test facilities PKL and ROCOM


Experiments on main steam line break in the test facilities PKL and ROCOM

Umminger, K.; Dennhardt, L.; Kliem, S.

Non-isolable main steam line breaks in PWRs cause a rapid depressurization of the affected steam generator. This leads to increased heat transfer from the primary to the secondary side and thereby to a fast cooldown transient on the primary side. Under certain boundary conditions the reactor pressure vessel integrity considering PTS (pressurized thermal shock) and potential recriticality following entrainment of colder water into the core area are important aspects to be assessed. Complementary tests in the PKL (system behavior) and ROCOM (mixing behavior in the RPV downcomer and lower plenum) facilities have been performed on this subject. This paper summarizes the main outcome of these experiments and their use for safety analysis.

  • Contribution to proceedings
    14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, 25.-30.09.2011, Toronto, Canada
    Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, paper 279
  • Lecture (Conference)
    14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, 25.-30.09.2011, Toronto, Canada

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Publ.-Id: 15835