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Hybrid simulation of BWR dynamics using a university research reactor

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:76070
The experimental verification of a hybrid reactor simulation (HRS) boiling water reactor control and diagnostic system (CDS) test bed has been accomplished. The testing was performed at the Penn State TRIGA reactor. The shape and frequency of oscillation of the limit cycles obtained with the HRS are similar to those observed in operating commercial BWRs. A CDS specifically designed to accommodate this type of anomaly can be experimentally verified using the research-reactor-based HRS.
OSTI ID:
76070
Report Number(s):
CONF-940602--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English