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Interpretation of experimental results from the CORA core melt progression experiments

Conference ·
OSTI ID:6174809
;
Data obtained from the CORA bundle heatup and melting experiments, performed at Kernforschungszentrum, Karlsruhe, Germany, are being analyzed at the Idaho National Engineering Laboratory. The analysis is being performed as part of a systematic review of core melt progression experiments for the United States Nuclear Regulatory Commission to (a) develop an improved understanding of important phenomena occurring during a severe accident, (b) to validate existing severe accident models, and (c) where necessary, develop improved models. An assessment of the variations in damage progression behavior because of variations in test parameters (a) bundle design and size, (b) system pressure, (c) slow cooling of the damaged bundles in argon versus rapid quenching in water, and (d) bundle inlet temperatures and flow rates is provided in the paper. The influence of uncertainties in important test conditions is also discussed. Specific results presented include (a) bundle temperature, (b) the onset and movement of the oxidation front within the bundle, (c) fuel rod ballooning and rod failure, and (d) melt relocation and associated material interactions between bundle components and structures. 12 refs., 16 figs., 2 tabs.
Research Organization:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Organization:
NRC; Nuclear Regulatory Commission, Washington, DC (United States)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6174809
Report Number(s):
EGG-M-91247; CONF-911107--42; ON: DE92003271
Country of Publication:
United States
Language:
English

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