Experiments on Main Steam Line Break in the Test Facilities PKL and ROCOM
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
O7-1 Pressurized Thermal Shock: General Studies

Authors:
Klaus Umminger (AREVA NP GmbH)
Lars Dennhardt (AREVA NP GmbH)
Sören Kliem (Helmholtz-Zentrum Dresden-Rossendorf)
  

Abstract

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 reactor pressure vessel (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.

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