ABSTRACT
This chapter shows how the VULCAIN code was used to define the HEVA 06 test with realistically simulated reactor accident conditions and, reciprocally, how large benefits may be achieved by performing such an experiment for the prediction of volatile fission products (F.P.) release. An analysis of core degradation computations performed with the VULCAIN code for the AF scenario was used to define the objectives and operating parameters of the HEVA 06 test. This experiment was designed to study F.P. release and behaviour at low pressure under realistic hydrogen conditions liable to occur in a steam-starved zone of a pressurised water reactor core during its degradation. The oxidation state of the zircaloy cladding, to be reproduced in the HEVA 06 test, was derived from VULCAIN computations carried out by using the CATHCART - PAWEL oxidation kinetics law.
