Analyses of eigenvalue bias and control rod worths in FFTF (Fast Flux Test Facility)

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:6299438

Nelson, J V; Dobbin, K D; Wootan, D W; Campbell, L R

The Fast Flux Test Facility (FFTF) core loading during its ninth operating cycle was significantly different from that of previous cycles because of the presence of the Core Demonstration Experiment (CDE). The CDE consists of a number of axially blanketed fuel assemblies and internal blankets prototypic of advanced oxide cores in Liquid Metal Reactors (LMR). In preparation for the Cycle 9 reload design effort, a careful assessment of control rod worth and reactivity calculations for Cycles 1 through 8 was made. The goal of this study was to establish calculational biases and reduce uncertainties factored into the reload design calculations. These analyses helped assure that the operational objectives for Cycle 9 were met.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6299438
• Report Number(s): HEDL-SA-3631-FP; CONF-870917-6; ON: DE87014380
• 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
CALCULATION METHODS
CONTROL ELEMENTS
CONTROL ROD WORTHS
EIGENVALUES
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUELS
LIQUID METAL COOLED REACTORS
MIXED OXIDE FUELS
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TEST REACTORS