Central fuel worth in the Fast Test Reactor (FTR) engineering mockup

Conference · Wed Jan 01 00:00:00 EST 1975

OSTI ID:7283924

Dobbin, K. D.; Daughtry, J. W.

An experiment was performed in the FTR-EMC to measure the total reactivity worth and the axial worth profile of withdrawing the central subassembly into the axial regions above the core. Calculations using three-dimensional X-Y-Z and two-dimensional R-Z models have been made to obtain reactivity worths for comparison with the experimental results. Another experiment measured the reactivity worth of replacing the fueled section of the central subassembly with sodium channel composition. The purposes of the analysis of this experiment are: (1) to determine if the C/E values obtained in the earlier three-dimensional calculations could be reproduced using another experiment from the FTR engineering mockup for comparison, (2) to determine what type of axial buckling adjustments are required to give the same calculated central fuel worths with a two-dimensional X-Y model that were obtained using the three-dimensional model, and (3) to obtain C/E values for the worths of an inner driver subassembly and an outer driver subassembly relative to sodium channel composition at the center of the EMC. A brief description of the experiments, a detailed explanation of the analytical methods, the measured and calculated results, and a comparison of these results.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: E(45-1)-2170
• OSTI ID: 7283924
• Report Number(s): HEDL-SA-997; CONF-751101-72; TRN: 76-014444
• Resource Relation: Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, San Francisco, CA, USA, 16 Nov 1975
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
REACTIVITY WORTHS
COMPARATIVE EVALUATIONS
DATA
MOCKUP
REACTOR CORES
EPITHERMAL REACTORS
FAST REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRUCTURAL MODELS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors