Fission rate ratios in the FTR engineering mockup

Conference · Tue Dec 31 23:00:00 EST 1974

OSTI ID:7188684

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

To evaluate neutron flux calculational methods, fission rates were measured in the FTR Engineering Mockup Critical (EMC) assembly, and calculated fission rates were obtained for comparison. Several variations of the analytical methods were used to investigate their suitability and calculation-versus-experiment (C/E) bias factors were obtained which can be used to adjust calculated fission rate ratios in the FTR. A brief description is given of the EMC configuration, the experiment, and the results of the experiments. The analytical methods are described, the calculated results are given, and comparisons are made between the experimental and analytical results.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AT(45-1)-2170
• OSTI ID: 7188684
• Report Number(s): HEDL-SA-998; CONF-751101-85
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ISOTOPES
COMPARATIVE EVALUATIONS
DATA
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FISSION SPECTRA
INFORMATION
KINETICS
LIQUID METAL COOLED REACTORS
MOCKUP
PLUTONIUM ISOTOPES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRUCTURAL MODELS
TEST REACTORS
URANIUM ISOTOPES