Automated reactivity anomaly surveillance in the Fast Flux Test Facility

Conference · Mon Dec 31 23:00:00 EST 1984

OSTI ID:6496370

Knutson, B J; Harris, R A; Honeyman, D J; Shook, A T; Krohn, C N

The automated 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.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6496370
• Report Number(s): HEDL-SA-3269FP; CONF-850903-14; ON: DE85018207
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALGORITHMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
MATHEMATICAL LOGIC
MONITORING
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SURVEILLANCE
TEST REACTORS