Reactivity anomalies in the FFTF (Fast Flux Test Facility): An evaluation of data from Cycles 1 through 8

Conference · Wed Apr 01 00:00:00 EST 1987

OSTI ID:5853136

Knutson, B. J.; Harris, R. A.

Experience using an automated core reactivity monitoring technique at the Fast Flux Test Facility (FFTF) through eight operating cycles is described. This technique relies on comparing predicted to measured rod positions to detect any anomalous (or unpredicted) core reactivity changes. Reactivity worth predictions of core state changes (e.g., temperature and irradiation changes) and compensating control rod movements are required for the rod position comparison. A substantial data base now exists to evaluate changes in temperature reactivity feedback effects operational in the FFTF, rod worth changes due to core loading, temperature and irradiation effects and burnup effects associated with transmutation of fuel materials. This report summarizes preliminary work of correlating zero power and at-power rod worth measurement data, calculated burnup rates and rod worths using the latest ENDF/B-V cross section set for each cycle to evaluate the prediction models and attempt to resolve observed reactivity anomalies. 2 figs., 2 tabs.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5853136
• Report Number(s): HEDL-SA-3712; CONF-8704383-1; ON: DE89014943
• Resource Relation: Conference: American Nuclear Society (ANS) topical meeting, Kennewick, WA, USA, Apr 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
REACTIVITY
BURNUP
CONTROL ELEMENTS
CONTROL ROD WORTHS
E CODES
FEEDBACK
REACTOR CORES
REACTOR MONITORING SYSTEMS
COMPUTER CODES
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220400* - Nuclear Reactor Technology- Control Systems
210500 - Power Reactors
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