학술논문

Fission rate ratios in the FTR engineering mockup
Document Type
Conference
Author
Source
Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, San Francisco, CA, USA, 16 Nov 1975
Subject
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS FFTF REACTOR
REACTOR KINETICS
COMPARATIVE EVALUATIONS
DATA
FISSION SPECTRA
MOCKUP
PLUTONIUM ISOTOPES
URANIUM ISOTOPES
ACTINIDE ISOTOPES
EPITHERMAL REACTORS
FAST REACTORS
INFORMATION
KINETICS
LIQUID METAL COOLED REACTORS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRUCTURAL MODELS
TEST REACTORS 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
Language
English
Abstract
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.