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Proceedings of the 22nd International QUENCH Workshop 18-20 October 2016, Karlsruhe Institute of Technology

Steinbrück, Martin

Abstract (englisch):
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 could be an enhanced oxidation of the Zircaloy cladding and other core materials 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 are the subject of the QUENCH program at KIT. The OECD/NEA International Standard Problem ISP-45 on QUENCH-06 as well as subsequent code activities have shown that the codes still have difficulties to calculate correctly the bundle behavior during reflood; especially thermal runaway is usually not predicted. Coolability of a degraded core is still a matter of high priority as was confirmed by the SARNET-SARP group as well as by OECD-GAMA repor ... mehr


Zugehörige Institution(en) am KIT Programm Nuclear Waste Management and Safety (NUSAFE) (NUSAFE)
Institut für Angewandte Materialien - Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Proceedingsband
Jahr 2016
Sprache Englisch
Identifikator ISBN: 978-3-923704-92-7
KITopen ID: 1000062563
HGF-Programm 32.02.11; LK 01
Verlag KIT, Karlsruhe
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