Blocked tube transient and failure analysis
Technical Report
·
OSTI ID:6563192
A thermal analysis was conducted using Version 7 of the MELT code to determine the temperature response of the fuel after a pressure tube coolant flow blockage. For this analysis, it was postulated that a tube became blocked by debris at the flow monitoring venturi. In the event of such a flow trip signal, the reactor would SCRAM due to a flow monitor system high flow. The residual reactivity and decay heat would result in boiling of the interstitial water resulting in tube voiding. From a previous RELAP run for a cold-leg cross-over break, the RELAP analysis predicts tube voiding at 30 seconds after the flow blockage.
- Research Organization:
- United Nuclear Industries, Inc., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-06-1857
- OSTI ID:
- 6563192
- Report Number(s):
- UNI-1148
- Country of Publication:
- United States
- Language:
- English
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