Simulation of the VVER-Type bundle experiment QUENCH-12 with ATHLET-CD

To ensure the coolability of an overheated core, reflood of the uncovered fuel elements is an essential accident management measure to terminate a severe accident transient in Light Water Reactors (LWR) and therefore to avoid further core degradation. From analysis of the TMI-2 accident it is known that an enhanced oxidation of the zircaloy cladding may occur before the water succeeds in cooling the fuel rods. This oxidation process results in a sharp temperature increase, hydrogen generation and can finally after fuel rod cladding failure lead to fission product release. For further development and validation of the program ATHLET-CD, post-test calculations of experiments creating a reflood scenario in a controlled and defined environment are used. One of these experiments is QUNECH-12 in which Zr1%Nb (E 110) fuel rod claddings are used. Typically, fuel rods of VVER reactors are made from this material. In this work, the QUENCH-12 experiment and its conduct will be presented followed by explanations of the modeling in ATHLET-CD version 2.2A. Results of ATHLET-CD simulating the test will be discussed in order to validate the code's ability to adequately calculate phenomena like hydrogen production and melt oxidation during reflooding of uncovered fuel rods of E 110. (orig.)