QUENCH Programme

QUENCH Programme at KIT

An important accident management measure for controlling severe accident transients in light water reactors (LWRs) is the injection of water to cool the degrading core. Flooding of the overheated core, which causes quenching of the fuel rods, is considered a worst-case scenario regarding hydrogen generation rates which should not exceed safety-relevant critical values. Before the water succeeds in cooling the uncovered core, there can be an enhanced oxidation of the Zircaloy cladding that in turn causes a sharp increase in temperature, hydrogen production, and fission product release. The complex physico-chemical processes during quenching and their mutual influence is not yet sufficiently known. In most of the code systems describing severe fuel damage the quench phenomena are only modeled in a simplified empirical manner. Therefore, a research program on reflood of an overheated core and corresponding topics is running at KIT, including large scale bundle tests, various kinds of separate-effects tests at IAM-AWP, model development and code application.

The QUENCH Program is embedded in the European Network of Excellence on Severe Accident Research SARNET 2

Save the date:
26th QUENCH Workshop 2020
*

17-19 November 2020; KIT

 

Cancelled as face-to-face event due to the Corona pandemic

Instead: Virtual event foreseen with reduced agenda focusing on ATF cladding and including the Kickoff Meeting for the planned NEA coordinated QUENCH-ATF Joint Undertaking

 

More information coming soon

 

* In cooperation with the International Atomic Energy Agency, IAEA