Published April 1987 | Version v1
Report Restricted

Reactivity anomalies in the FFTF [Fast Flux Test Facility]

  • 1. Hanford Engineering Development Lab., Richland, WA (USA)

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

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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).

Optional Information

Contract/Grant/Project number
Contract DOE AC06-76FF02170
Secondary number(s)
CONF-8704383--1.