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Reactivity anomaly surveillance in the Fast Flux Test Facility through cycle 3

Conference ·
OSTI ID:6277810
The technique for monitoring core reactivity during power operation used at the Fast Flux Test Facility (FFTF) is described. This technique relies on comparing predicted to measured rod positions to detect any anomalous (or unpredicted) core reactivity changes. It is implemented on the Plant Data System (PDS) computer and thus provides rapid indication of any abnormal core conditions. The prediction algorithms use thermal-hydraulic, control rod position and neutron flux sensor information to predict the core reactivity state. Initial results of using this technique based mainly on theoretical formulations is presented. The results show that the reactivity changes due to increasing reactor power (power defect) and burnup of the fuel were within approx. 16% of predicted values. To increase the sensitivity and accuracy of this technique, the prediction algorithms were calibrated to actual operating data. The work of calibrating this technique and the results of using the calibrated technique up through the third full operating cycle are summarized.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
Sponsoring Organization:
DOE
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6277810
Report Number(s):
HEDL-SA-3108-FP; CONF-840901-20; ON: DE85001065
Resource Type:
Conference paper/presentation
Conference Information:
ANS topical meeting on reactor physics and shielding, Chicago, IL, USA, 17 Sep 1984
Country of Publication:
United States
Language:
English