Reactivity anomalies in the FFTF [Fast Flux Test Facility]
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - OSTI as DE89014943; US Govt. Printing Office Dep.
Files
Additional details
Additional titles
- Subtitle (English)
- An evaluation of data from Cycles 1 through 8
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- HEDL-SA--3712
Conference
- Title
- American Nuclear Society (ANS) topical meeting.
- Dates
- Apr 1987.
- Place
- Kennewick, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20079954
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CONTROL ELEMENTS; CONTROL ROD WORTHS; E CODES; FEEDBACK; FFTF REACTOR; REACTIVITY; REACTOR CORES; REACTOR MONITORING SYSTEMS
- Descriptors DEC
- COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DOE AC06-76FF02170
- Secondary number(s)
- CONF-8704383--1.